National Library of Energy BETA

Sample records for model involves iterative

  1. Modeling Results For the ITER Cryogenic Fore Pump. Final Report

    SciTech Connect (OSTI)

    Pfotenhauer, John M.; Zhang, Dongsheng

    2014-03-31

    A numerical model characterizing the operation of a cryogenic fore-pump (CFP) for ITER has been developed at the University of Wisconsin – Madison during the period from March 15, 2011 through June 30, 2014. The purpose of the ITER-CFP is to separate hydrogen isotopes from helium gas, both making up the exhaust components from the ITER reactor. The model explicitly determines the amount of hydrogen that is captured by the supercritical-helium-cooled pump as a function of the inlet temperature of the supercritical helium, its flow rate, and the inlet conditions of the hydrogen gas flow. Furthermore the model computes the location and amount of hydrogen captured in the pump as a function of time. Throughout the model’s development, and as a calibration check for its results, it has been extensively compared with the measurements of a CFP prototype tested at Oak Ridge National Lab. The results of the model demonstrate that the quantity of captured hydrogen is very sensitive to the inlet temperature of the helium coolant on the outside of the cryopump. Furthermore, the model can be utilized to refine those tests, and suggests methods that could be incorporated in the testing to enhance the usefulness of the measured data.

  2. Mixed direct-iterative methods for boundary integral formulations of continuum dielectric solvation models

    SciTech Connect (OSTI)

    Corcelli, S.A.; Kress, J.D.; Pratt, L.R.

    1995-08-07

    This paper develops and characterizes mixed direct-iterative methods for boundary integral formulations of continuum dielectric solvation models. We give an example, the Ca{sup ++}{hor_ellipsis}Cl{sup {minus}} pair potential of mean force in aqueous solution, for which a direct solution at thermal accuracy is difficult and, thus for which mixed direct-iterative methods seem necessary to obtain the required high resolution. For the simplest such formulations, Gauss-Seidel iteration diverges in rare cases. This difficulty is analyzed by obtaining the eigenvalues and the spectral radius of the non-symmetric iteration matrix. This establishes that those divergences are due to inaccuracies of the asymptotic approximations used in evaluation of the matrix elements corresponding to accidental close encounters of boundary elements on different atomic spheres. The spectral radii are then greater than one for those diverging cases. This problem is cured by checking for boundary element pairs closer than the typical spatial extent of the boundary elements and for those cases performing an ``in-line`` Monte Carlo integration to evaluate the required matrix elements. These difficulties are not expected and have not been observed for the thoroughly coarsened equations obtained when only a direct solution is sought. Finally, we give an example application of hybrid quantum-classical methods to deprotonation of orthosilicic acid in water.

  3. US ITER | Media Corner

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    In Jacob's Room at US ITER In Jacob's Room at US ITER College Student Models, Simulates and Designs a Cooling Subsystem for the ITER Tokamak -Agatha Bardoel Published June 24, 2011 US ITER Project Manger Ned Sauthoff and ITER Director-General Osamu Motojima Jacob Clary is working under the guidance of Dr. Juan Ferrada to develop a cooling loop model. Nineteen-year-olds are not often found modeling and simulating a novel design for a cooling subsystem of the giant international Tokamak reactor

  4. US ITER | Media Corner

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Neutronics at Wisconsin, ORNL advances ITER shielding and international collaboration "Neutronics" at Wisconsin, ORNL advances ITER shielding and international collaboration Computer codes calculate nuclear heating, neutron radiation damage and activation of fusion reactor materials. -Lynne Degitz Published June 18, 2012 A neutronics model of ITER is behind (left to right) Ed Marriott, Tim Bohm, Paul Wilson, Mohamed Sawan and Ahmad Ibrahim, US ITER researchers at the University of

  5. A new frequency domain arc furnace model for iterative harmonic analysis

    SciTech Connect (OSTI)

    Mayordomo, J.G.; Beites, L.F.; Asensi, R.; Izzeddine, M.; Zabala, L.; Amantegui, J.

    1997-10-01

    This paper presents a new frequency domain Arc Furnace model for Iterative Harmonic Analysis (IHA) by means of a Newton method. Powerful analytical expressions for harmonic currents and their derivatives are obtained under the balanced conditions of the system. The model offers a three phase configuration where there is no path for homopolar currents. Moreover, it contemplates continuous and discontinuous evolution of the arc current. The solution obtained is validated by means of time domain simulations. Finally, the model was integrated in a harmonic power flow where studies have been performed in a network with more than 700 busbars and 7 actual Arc Furnace Loads.

  6. US ITER

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Production toroidal field coil integrated and jacketed at High Performance Magnetics in Tallahassee, FL. Photo: US ITER The US ITER project engages more than 500 companies, ...

  7. Validation of the thermal transport model used for ITER startup scenario predictions with DIII-D experimental data

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Casper, T. A.; Meyer, W. H.; Jackson, G. L.; Luce, T. C.; Hyatt, A. W.; Humphreys, D. A.; Turco, F.

    2010-12-08

    We are exploring characteristics of ITER startup scenarios in similarity experiments conducted on the DIII-D Tokamak. In these experiments, we have validated scenarios for the ITER current ramp up to full current and developed methods to control the plasma parameters to achieve stability. Predictive simulations of ITER startup using 2D free-boundary equilibrium and 1D transport codes rely on accurate estimates of the electron and ion temperature profiles that determine the electrical conductivity and pressure profiles during the current rise. Here we present results of validation studies that apply the transport model used by the ITER team to DIII-D discharge evolutionmore » and comparisons with data from our similarity experiments.« less

  8. US ITER | Media Corner

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    toroidal field conductor fabrication advances US toroidal field conductor fabrication advances -Lynne Degitz Published January 7, 2013 A neutronics model of ITER is behind (left to right) Ed Marriott, Tim Bohm, Paul Wilson, Mohamed Sawan and Ahmad Ibrahim, US ITER researchers at the University of Wisconsin. Superconducting strand is cabled at New England Wire Technologies on 2.5 meter wide by 2 meter tall spools before shipment to Florida for conductor jacketing. Photo: NEWT . US ITER and its

  9. US ITER | Media Corner

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    US ITER preps for high performance plasma heating US ITER preps for high performance plasma heating New test results and innovations advance ion cyclotron high power transmission line progress for US ITER -Lynne Degitz Published April 29, 2014 A "toy"-sized, but accurately scaled, version of the ITER central solenoid (left) with one of the 18 toroidal field coils, printed on a desktop 3D printer. The pink oval represents the plasma. Notice the action figure at right showing the model's

  10. SU-E-I-33: Initial Evaluation of Model-Based Iterative CT Reconstruction Using Standard Image Quality Phantoms

    SciTech Connect (OSTI)

    Gingold, E; Dave, J

    2014-06-01

    Purpose: The purpose of this study was to compare a new model-based iterative reconstruction with existing reconstruction methods (filtered backprojection and basic iterative reconstruction) using quantitative analysis of standard image quality phantom images. Methods: An ACR accreditation phantom (Gammex 464) and a CATPHAN600 phantom were scanned using 3 routine clinical acquisition protocols (adult axial brain, adult abdomen, and pediatric abdomen) on a Philips iCT system. Each scan was acquired using default conditions and 75%, 50% and 25% dose levels. Images were reconstructed using standard filtered backprojection (FBP), conventional iterative reconstruction (iDose4) and a prototype model-based iterative reconstruction (IMR). Phantom measurements included CT number accuracy, contrast to noise ratio (CNR), modulation transfer function (MTF), low contrast detectability (LCD), and noise power spectrum (NPS). Results: The choice of reconstruction method had no effect on CT number accuracy, or MTF (p<0.01). The CNR of a 6 HU contrast target was improved by 167% with iDose4 relative to FBP, while IMR improved CNR by 145367% across all protocols and dose levels. Within each scan protocol, the CNR improvement from IMR vs FBP showed a general trend of greater improvement at lower dose levels. NPS magnitude was greatest for FBP and lowest for IMR. The NPS of the IMR reconstruction showed a pronounced decrease with increasing spatial frequency, consistent with the unusual noise texture seen in IMR images. Conclusion: Iterative Model Reconstruction reduces noise and improves contrast-to-noise ratio without sacrificing spatial resolution in CT phantom images. This offers the possibility of radiation dose reduction and improved low contrast detectability compared with filtered backprojection or conventional iterative reconstruction.

  11. US ITER | Jobs

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Postings Careers in Fusion Science ITER Jobs Home > Jobs > US ITER Positions US ITER Positions US

  12. US ITER | Media Corner

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    of Terms Project Background Creating a Star - The Global ITER Partnership Photo Books ITER Progress in Pictures 2015 (US edition) ITER Progress in Pictures 2015 (ITER...

  13. US ITER | About

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    US ITER About US ITER ABOUT US ITER | WHY FUSION? | DOING BUSINESS WITH US ITER | MEDIA CORNER | JOBS | CONTACT US About US ITER US Hardware Contributions About US ITER Home > About US ITER Background US ITER is a DOE Office of Science project hosted by Oak Ridge National Laboratory in Tennessee. Partner labs are Princeton Plasma Physics Laboratory and Savannah River National Laboratory. The US is a partner nation in ITER, an unprecedented international collaboration of scientists and

  14. Statistical model based iterative reconstruction (MBIR) in clinical CT systems: Experimental assessment of noise performance

    SciTech Connect (OSTI)

    Li, Ke; Tang, Jie; Chen, Guang-Hong

    2014-04-15

    Purpose: To reduce radiation dose in CT imaging, the statistical model based iterative reconstruction (MBIR) method has been introduced for clinical use. Based on the principle of MBIR and its nonlinear nature, the noise performance of MBIR is expected to be different from that of the well-understood filtered backprojection (FBP) reconstruction method. The purpose of this work is to experimentally assess the unique noise characteristics of MBIR using a state-of-the-art clinical CT system. Methods: Three physical phantoms, including a water cylinder and two pediatric head phantoms, were scanned in axial scanning mode using a 64-slice CT scanner (Discovery CT750 HD, GE Healthcare, Waukesha, WI) at seven different mAs levels (5, 12.5, 25, 50, 100, 200, 300). At each mAs level, each phantom was repeatedly scanned 50 times to generate an image ensemble for noise analysis. Both the FBP method with a standard kernel and the MBIR method (Veo{sup }, GE Healthcare, Waukesha, WI) were used for CT image reconstruction. Three-dimensional (3D) noise power spectrum (NPS), two-dimensional (2D) NPS, and zero-dimensional NPS (noise variance) were assessed both globally and locally. Noise magnitude, noise spatial correlation, noise spatial uniformity and their dose dependence were examined for the two reconstruction methods. Results: (1) At each dose level and at each frequency, the magnitude of the NPS of MBIR was smaller than that of FBP. (2) While the shape of the NPS of FBP was dose-independent, the shape of the NPS of MBIR was strongly dose-dependent; lower dose lead to a redder NPS with a lower mean frequency value. (3) The noise standard deviation (?) of MBIR and dose were found to be related through a power law of ????(dose){sup ??} with the component ? ? 0.25, which violated the classical ????(dose){sup ?0.5} power law in FBP. (4) With MBIR, noise reduction was most prominent for thin image slices. (5) MBIR lead to better noise spatial uniformity when compared with FBP. (6) A composite image generated from two MBIR images acquired at two different dose levels (D1 and D2) demonstrated lower noise than that of an image acquired at a dose level of D1+D2. Conclusions: The noise characteristics of the MBIR method are significantly different from those of the FBP method. The well known tradeoff relationship between CT image noise and radiation dose has been modified by MBIR to establish a more gradual dependence of noise on dose. Additionally, some other CT noise properties that had been well understood based on the linear system theory have also been altered by MBIR. Clinical CT scan protocols that had been optimized based on the classical CT noise properties need to be carefully re-evaluated for systems equipped with MBIR in order to maximize the method's potential clinical benefits in dose reduction and/or in CT image quality improvement.

  15. US ITER | Jobs

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Postings Careers in Fusion Science ITER Jobs Home > Jobs > International Job Postings International ITER Postions International

  16. US ITER | Media Corner

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    India DA Project Director Visits US ITER Project Office India DA Project Director Visits US ITER Project Office Published Janaury 5, 2012 India DA Project Director Visits US ITER Project Office US ITER project manager Ned Sauthoff and India DA project director Shishir Deshpande share a laugh while watching a skit during the US ITER staff holiday luncheon. Photo: US ITER/ORNL Shishir P. Deshpande, Project Director for the ITER India Domestic Agency, visited the US ITER Project Office on December

  17. US ITER | Media Corner

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Corner Fact Sheets Hydrogen Fusion ITER Project US ITER Progress US ITER Participants More Project Background Creating a Star - The Global ITER Partnership Features and Highlights Winding completed on first central solenoid module [ITER Newsline, Arpril 11, 2016] Fusion diagnostics heat up across the US [US ITER, October 22, 2015] Preparing a unique fabrication line for the central solenoid modules [US ITER, September 14, 2015] Central solenoid insert coil confirms conductor readiness for ITER

  18. IDC RE-Engineering Phase 2 Iteration E1 Use Case Model Survey.

    SciTech Connect (OSTI)

    Harris, James M.; Carr, Dorthe B.; Coram, Jamie L.

    2016-01-01

    This document contains the brief descriptions for the actors and use cases contained in the IDC Use Case Model.

  19. US ITER | Contact Us

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Organizational Charts ABOUT US ITER | WHY FUSION? | DOING BUSINESS WITH US ITER | MEDIA CORNER | JOBS | CONTACT US Visitor Information Key Contact Staff Directory Organizational Charts U.S. ITER Contacts Home > Contact Us> Organizational Charts Organizational Charts US ITER Organizational Chart Oak Ridge National Laboratory Organizational Chart ITER Organization (IO) Structure Chart ITER International Department of Energy Office of Science Oak Ridge National Laboratory Princeton Plasma

  20. US ITER | Media Corner

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    9 News Archive: 2009 Schedule Concerns Delay ITER's Go-Ahead [Science Magazine, November 27, 2009] ITER council delays project [Physics Today, November 20, 2009] ITER Blueprints Near Completion, But Financial Hurdles Lie Ahead [Science Magazine, November 13, 2009] ORNL director testifies on ITER, fusion research [Knoxville News Sentinel, October 29, 2009] Herron named deputy director of US ITER [Knoxville News Sentinel, October 15, 2009] US ITER awards $33.6M for magnet materials [Knoxville News

  1. US ITER | Media Corner

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    New Division Management in Place at US ITER New Division Management in Place at US ITER Published September 20, 2011 After an extensive international search, US ITER selected John Bumgardner as the US ITER nuclear systems division director and John Haines as the US ITER non-nuclear systems division director. These new managers will provide important leadership as the project transitions from research and design to the engagement of industry in fabrication of US ITER hardware contributions. Both

  2. US ITER | Media Corner

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Building the Heartbeat of ITER Building the Heartbeat of ITER Preparing a unique fabrication line for the central solenoid modules -Lynne Degitz September 14, 2015 A partial view...

  3. US ITER | Doing Business

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    US ITER > Business Opportunties > For Vendors > Tokamak Cooling Water System Opportunities Tokamak Cooling Water System (TCWS) Opportunities US ITER has contracted with AREVA...

  4. Characterization of a commercial hybrid iterative and model-based reconstruction algorithm in radiation oncology

    SciTech Connect (OSTI)

    Price, Ryan G.; Vance, Sean; Cattaneo, Richard; Elshaikh, Mohamed A.; Chetty, Indrin J.; Glide-Hurst, Carri K.; Schultz, Lonni

    2014-08-15

    Purpose: Iterative reconstruction (IR) reduces noise, thereby allowing dose reduction in computed tomography (CT) while maintaining comparable image quality to filtered back-projection (FBP). This study sought to characterize image quality metrics, delineation, dosimetric assessment, and other aspects necessary to integrate IR into treatment planning. Methods: CT images (Brilliance Big Bore v3.6, Philips Healthcare) were acquired of several phantoms using 120 kVp and 25800 mAs. IR was applied at levels corresponding to noise reduction of 0.890.55 with respect to FBP. Noise power spectrum (NPS) analysis was used to characterize noise magnitude and texture. CT to electron density (CT-ED) curves were generated over all IR levels. Uniformity as well as spatial and low contrast resolution were quantified using a CATPHAN phantom. Task specific modulation transfer functions (MTF{sub task}) were developed to characterize spatial frequency across objects of varied contrast. A prospective dose reduction study was conducted for 14 patients undergoing interfraction CT scans for high-dose rate brachytherapy. Three physicians performed image quality assessment using a six-point grading scale between the normal-dose FBP (reference), low-dose FBP, and low-dose IR scans for the following metrics: image noise, detectability of the vaginal cuff/bladder interface, spatial resolution, texture, segmentation confidence, and overall image quality. Contouring differences between FBP and IR were quantified for the bladder and rectum via overlap indices (OI) and Dice similarity coefficients (DSC). Line profile and region of interest analyses quantified noise and boundary changes. For two subjects, the impact of IR on external beam dose calculation was assessed via gamma analysis and changes in digitally reconstructed radiographs (DRRs) were quantified. Results: NPS showed large reduction in noise magnitude (50%), and a slight spatial frequency shift (?0.1 mm{sup ?1}) with application of IR at L6. No appreciable changes were observed for CT-ED curves between FBP and IR levels [maximum difference ?13 HU for bone (?1% difference)]. For uniformity, differences were ?1 HU between FBP and IR. Spatial resolution was well conserved; the largest MTF{sub task} decrease between FBP and IR levels was 0.08 A.U. No notable changes in low-contrast detectability were observed and CNR increased substantially with IR. For the patient study, qualitative image grading showed low-dose IR was equivalent to or slightly worse than normal dose FBP, and is superior to low-dose FBP (p < 0.001 for noise), although these did not translate to differences in CT number, contouring ability, or dose calculation. The largest CT number discrepancy from FBP occurred at a bone/tissue interface using the most aggressive IR level [?1.2 4.9 HU (range: ?17.612.5 HU)]. No clinically significant contour differences were found between IR and FBP, with OIs and DSCs ranging from 0.85 to 0.95. Negligible changes in dose calculation were observed. DRRs preserved anatomical detail with <2% difference in intensity from FBP combined with aggressive IRL6. Conclusions: These results support integrating IR into treatment planning. While slight degradation in edges and shift in texture were observed in phantom, patient results show qualitative image grading, contouring ability, and dosimetric parameters were not adversely affected.

  5. Review of recent experimental and modeling progress in the lower hybrid range of frequencies at ITER relevant parameters

    SciTech Connect (OSTI)

    Bonoli, Paul T.

    2014-02-12

    Progress in experiment and simulation capability in the lower hybrid range of frequencies (LHRF) at ITER relevant parameters is reviewed. Use of LH power in reactor devices is motivated in terms of its potential for efficient off-axis current profile control. Recent improvements in simulation capability including the development of full-wave field solvers, inclusion of the scrape off layer (SOL) in wave propagation codes, the use of coupled ray tracing / full-wave / 3D (r v{sub ?}, v{sub ?}) Fokker Planck models, and the inclusion of nonlinear broadening effects in ray tracing / Fokker Planck codes are discussed. Experimental and modeling results are reviewed which are aimed at understanding the spectral gap problem in LH current drive (LHCD) and the density limit that has been observed in LHCD experiments. Physics mechanisms that could be operative in these experiments are discussed, including toroidally induced variations in the parallel wavenumber, nonlinear broadening of the pump wave, scattering of LH waves from density fluctuations in the SOL, and spectral broadening at the plasma edge via full-wave effects.

  6. Review of recent experimental and modeling progress in the lower hybrid range of frequencies at ITER relevant parameters

    SciTech Connect (OSTI)

    Bonoli, Paul T.

    2014-06-15

    Progress in experiment and simulation capability in the lower hybrid range of frequencies at ITER relevant parameters is reviewed. Use of LH power in reactor devices is motivated in terms of its potential for efficient off-axis current profile control. Recent improvements in simulation capability including the development of full-wave field solvers, inclusion of the scrape off layer (SOL) in wave propagation codes, the use of coupled ray tracing/full-wave/3D (r v{sub ?}, v{sub //}) Fokker Planck models, and the inclusion of wave scattering as well as nonlinear broadening effects in ray tracing / Fokker Planck codes are discussed. Experimental and modeling results are reviewed which are aimed at understanding the spectral gap problem in LH current drive (LHCD) and the density limit that has been observed and mitigated in LHCD experiments. Physics mechanisms that could be operative in these experiments are discussed, including toroidally induced variations in the parallel wavenumber, nonlinear broadening of the pump wave, scattering of LH waves from density fluctuations in the SOL, and spectral broadening at the plasma edge via full-wave effects.

  7. A model of lipid-free Apolipoprotein A-I revealed by iterative molecular dynamics simulation

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Zhang, Xing; Lei, Dongsheng; Zhang, Lei; Rames, Matthew; Zhang, Shengli

    2015-03-20

    Apolipoprotein A-I (apo A-I), the major protein component of high-density lipoprotein, has been proven inversely correlated to cardiovascular risk in past decades. The lipid-free state of apo A-I is the initial stage which binds to lipids forming high-density lipoprotein. Molecular models of lipid-free apo A-I have been reported by methods like X-ray crystallography and chemical cross-linking/mass spectrometry (CCL/MS). Through structural analysis we found that those current models had limited consistency with other experimental results, such as those from hydrogen exchange with mass spectrometry. Through molecular dynamics simulations, we also found those models could not reach a stable equilibrium state. Therefore,more » by integrating various experimental results, we proposed a new structural model for lipidfree apo A-I, which contains a bundled four-helix N-terminal domain (1–192) that forms a variable hydrophobic groove and a mobile short hairpin C-terminal domain (193–243). This model exhibits an equilibrium state through molecular dynamics simulation and is consistent with most of the experimental results known from CCL/MS on lysine pairs, fluorescence resonance energy transfer and hydrogen exchange. This solution-state lipid-free apo A-I model may elucidate the possible conformational transitions of apo A-I binding with lipids in high-density lipoprotein formation.« less

  8. A model of lipid-free Apolipoprotein A-I revealed by iterative molecular dynamics simulation

    SciTech Connect (OSTI)

    Zhang, Xing; Lei, Dongsheng; Zhang, Lei; Rames, Matthew; Zhang, Shengli

    2015-03-20

    Apolipoprotein A-I (apo A-I), the major protein component of high-density lipoprotein, has been proven inversely correlated to cardiovascular risk in past decades. The lipid-free state of apo A-I is the initial stage which binds to lipids forming high-density lipoprotein. Molecular models of lipid-free apo A-I have been reported by methods like X-ray crystallography and chemical cross-linking/mass spectrometry (CCL/MS). Through structural analysis we found that those current models had limited consistency with other experimental results, such as those from hydrogen exchange with mass spectrometry. Through molecular dynamics simulations, we also found those models could not reach a stable equilibrium state. Therefore, by integrating various experimental results, we proposed a new structural model for lipidfree apo A-I, which contains a bundled four-helix N-terminal domain (1–192) that forms a variable hydrophobic groove and a mobile short hairpin C-terminal domain (193–243). This model exhibits an equilibrium state through molecular dynamics simulation and is consistent with most of the experimental results known from CCL/MS on lysine pairs, fluorescence resonance energy transfer and hydrogen exchange. This solution-state lipid-free apo A-I model may elucidate the possible conformational transitions of apo A-I binding with lipids in high-density lipoprotein formation.

  9. US ITER | Doing Business

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    U.S. ITER > Business Opportunities Business Opportunities U.S. ITER International ITER International Organization (IO) Competitive Task Agreements ITER International Department of Energy Office of Science Oak Ridge National Laboratory Princeton Plasma Physics Laboratory Savannah River National Laboratory Last updated:

  10. US ITER | Jobs

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    US ITER Jobs ABOUT US ITER | WHY FUSION? | DOING BUSINESS WITH US ITER | MEDIA CORNER | JOBS | CONTACT US US Job Postings International Job Postings Careers in Fusion Science ITER Jobs Home > US ITER Jobs Be a Part of Something Big! US ITER is a Department of Energy multi-laboratory project that executes the US contributions to ITER for the US. The US is a non-host partner in the seven-member international collaboration between the United States, China, India, Japan, Korea, Russia, and the

  11. US ITER | Doing Business

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Business Opportunties > ITER Clauses, Documents & Forms ITER Clauses, Documents & Forms Technical Proposal Disclosure Policy (April 2013) Identification of Background Intellectual Property by Prospective Subcontractors QA/QC Questionnaire Required Coordination with ITER Logistical Services Provider (April 2013) Patent Rights - Acquisition by the Government - ITER (March 2007) Exhibit 1B Patent Rights - Retention by the Seller (Short Form) - ITER (August 20, 2015) Exhibit 1C Exhibit 9

  12. US ITER | Jobs

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Postings Careers in Fusion Science ITER Jobs Home > Jobs > Careers in Fusion Science Learn More About Working at US ITER and Careers in Fusion Science Jan Berry Takes a Different Path (US ITER Tokamak Cooling Water System Team Leader) Ted Biewer: An International Career in Plasma Diagnostics (Fusion Energy Division, ORNL) video Frank Casella: Assuring Safety and Quality (US ITER Quality Assurance Officer) Kevin Chan: Optimizing Superconducting Strand (US ITER Toroidal Field Coil Conductor

  13. US ITER | Media Corner

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    ITER's central magnet requires a powerful support cage ITER's central magnet requires a powerful support cage Prototypes for the central solenoid support components have been fabricated and are being tested -Lynne Degitz Published May 21, 2013 US ITER is building one of the world's largest and most powerful electromagnets to energize the ITER tokamak, a device that confines plasma in the shape of a doughnut. The 13 meter tall central solenoid will be located in the heart of the ITER fusion

  14. US ITER | Media Corner

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Solutions developed for housing ITER diagnostics Solutions developed for housing ITER diagnostics US ITER is a strong contributor in plan to enhance international sharing of prime ITER real estate -Lynne Degitz Published March 27, 2013 Modular approach to housing the extensive diagnostic systems. Princeton Plasma Physics Laboratory's Russ Feder (left) and Dave Johnson developed key features for a modular approach to housing the extensive diagnostic systems that will be installed on the ITER

  15. US ITER | Media Corner

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    US Production of Miles of Superconducting Wire is Under Way for ITER's Super-Sized Toroidal Field Magnets US Production of Miles of Superconducting Wire is Under Way for ITER's Super-Sized Toroidal Field Magnets -Agatha Bardoel Published February 22, 2012 US ITER Toridal Field Coil Conductor US ITER toroidal field coil conductor production requires miles of niobium-tin superconducting wire. Photo: Luvata Waterbury, Inc. The ITER experimental fusion facility, now under construction in southern

  16. US ITER | Media Corner

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Videos US ITER Moving Forward US ITER Moving Forward (2012) Ned Sauthoff and Susan McGinnis - Fusion Reaction Energy for the Future (2011) Ned Sauthoff and Susan McGinnis - Fusion Reaction Fusion Reaction in a Tokamak (2010) Project Manager Ned Sauthoff talks about US ITER Project Manager Ned Sauthoff talks about US ITER (2009) Videos from the Around the World of Fusion (Link to complete list.) Fusion Energy Production by Neutral Particle Injection This visualization demonstrates how the ITER

  17. US ITER | Doing Business

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    ITER US ITER Procurement Division is responsible for the acquisition of goods and services for the US ITER project. Business Opportunities US: Upcoming US ITER Procurements US: Business Opportunities with Other Partner Laboratories International: Calls for Nominations, Calls for Expertise and Market Surveys/Requests for Interest International: Opportunities with Other International Partners ITER International Organization (IO) Competitive Task Agreements. For Vendors Vendors wishing to do

  18. US ITER | Media Corner

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Central solenoid insert coil confirms conductor readiness for ITER Central solenoid insert coil confirms conductor readiness for ITER Central solenoid insert coil confirms conductor readiness for ITER -Lynne Degitz Published August 13, 2015 The insert coil being lowered into the test facility at Naka, Japan. The insert coil being lowered into the test facility at Naka, Japan. Photo: JAEA In another step towards building the ITER fusion reactor, the US ITER team worked with international partners

  19. US ITER | Media Corner

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    ITER pump design benefits from testing at ORNL Spallation Neutron Source cryogenic facility ITER pump design benefits from testing at ORNL Spallation Neutron Source cryogenic facility ITER pump design benefits from testing at ORNL Spallation Neutron Source cryogenic facility -Lynne Degitz Published August 4, 2015 Robert Duckworth oversaw the testing of the 9-foot tall ITER cryoviscous compress pump prototype at the Spallation Neutron Source cryogenic test facility. Photo: US ITER/ORNL. Robert

  20. US ITER | Media Corner

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    US delivers multiple "firsts" for ITER site US delivers multiple "firsts" for ITER site Conductor for toroidal field magnets, drain tanks and electrical components are being delivered to Europe for installation at the ITER site -Lynne Degitz March 19, 2015 Conductor for toroidal field magnets A close-up view of toroidal field production conductor. The conductor delivered in January is approximately 800 meters in length. Photo: US ITER As the international ITER magnetic fusion

  1. US ITER | About

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    ITER Magnet System ITER Magnet System (WBS 1.1.1) The ITER Magnet System magnetically confines, shapes and controls the plasma inside the tokamak vacuum vessel. For maximum efficiency and to limit energy consumption, ITER uses superconducting magnets that lose their resistance when cooled to very low temperatures. The magnet system for ITER consists of: 18 toroidal field (TF) coils | more on US contribution Central solenoid (CS) with 6 segments | more on US contribution 6 poloidal field (PF)

  2. US ITER | Media Corner

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    UT Magnet Lab Advances US ITER and Next Generation of Engineers, Scientists UT Magnet Lab Advances US ITER and Next Generation of Engineers, Scientists -Agatha Bardoel Published December 29, 2011 UT Magnet Lab Sample of glass/epoxy composite produced at the MDL for US ITER magnet insulator testing. Photo: US ITER/ORNL Tucked away in an unassuming building off Pellissippi Parkway in Knoxville, The University of Tennessee's Magnet Development Laboratory is under contract to the US ITER project for

  3. US ITER Moving Forward

    ScienceCinema (OSTI)

    US ITER / ORNL

    2012-03-16

    US ITER Project Manager Ned Sauthoff, joined by Wayne Reiersen, Team Leader Magnet Systems, and Jan Berry, Team Leader Tokamak Cooling System, discuss the U.S.'s role in the ITER international collaboration.

  4. US ITER | Media Corner

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    New Procurement Arrangement Signed for Low Field Side Reflectometer Diagnostic New Procurement Arrangement Signed for Low Field Side Reflectometer Diagnostic -Agatha Bardoel Published June 21, 2012 US ITER Project Manger Ned Sauthoff and ITER Director-General Osamu Motojima US ITER Project Manager Ned Sauthoff and ITER Director-General Osamu Motojima sign the low field side reflectometer Procurement Agreement on June 20, 2012 in Washington, DC. This diagnostic system will monitor electron

  5. US ITER | Media Corner

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    fabrication of early delivery components for ITER advances US fabrication of early delivery components for ITER advances Delivery of tokamak cooling water system drain tanks will begin in 2014 -Katie Elyce Jones Published August 19, 2013 Vacuum Pressure Impregnation Vessel Drain tank heads, shown in fabrication at ODOM Industries in Milford Ohio, will be assembled at Joseph Oat Corporation in Camden, New Jersey. Photo: US ITER/ORNL Drain tank fabrication for ITER's tokamak cooling water system

  6. US ITER | Media Corner

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Newsletter Newsletter December 2015 July 2015 November 2014 February 2014 July 2013 January 2013 May 2012 December 2011 July 2011 March 2011 September 2010 Subscribe to the US ITER Newsletter Need an Expert? Media are welcome to contact Mark Uhran for assistance in reaching an appropriate US ITER expert. US ITER staff members are also available for presentations on fusion energy and the ITER project to technical, civic, community, and student groups. To make arrangements for a speaker, please

  7. INSIDE: ITER Site Progress

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Industry, Universities and Labs Job Openings Upcoming Events ITER's Central Magnet Requires a Powerful Support Cage Prototypes for the central solenoid support components have been fabricated and are being tested US ITER is building one of the world's largest and most powerful electromagnets to energize the ITER tokamak, a device that confines plasma in the shape of a doughnut. The 13 meter tall central solenoid will be located in the heart of the ITER fusion experiment. In order to maintain

  8. US ITER | About

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Diagnostics Diagnostics (WBS 1.5.3) Fact Sheet ITER Diagnostics Image Highlighted in pink: US contributions to ITER diagnostics. The US is responsible for 14% of port-based diagnostic systems, including integration of 4 diagnostic port plugs, plus 7 instrumentation systems out of a total of approximately 40 individual diagnostic systems. The European Union, Japan, the Russian Federation, China, Korea, and India are also contributing to ITER diagnostics. ITER diagnostic systems provide

  9. US ITER | Media Corner

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    US ITER Major Vendors, Project Director to Speak at FPA Annual Meeting US ITER Major Vendors, Project Director to Speak at FPA Annual Meeting in December Published September 28, 2011 Speakers from US ITER contractors Areva Federal Services and General Atomics, plus US ITER project director Ned Sauthoff will be among the presenters at the 32nd annual Fusion Power Associates meeting and symposium titled "Fusion Energy: Expectations" on December 14-15, 2011 in Washington, DC. A proposed

  10. US ITER | Doing Business

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Opportunties > For Vendors For Vendors US ITER Vendor Database (For US ITER internal use only) Vendor Account Status System ORNL Procurement ITER International Department of Energy Office of Science Oak Ridge National Laboratory Princeton Plasma Physics Laboratory Savannah River National Laboratory Last updated: 02/24

  11. ITER helium ash accumulation

    SciTech Connect (OSTI)

    Hogan, J.T.; Hillis, D.L.; Galambos, J.; Uckan, N.A. ); Dippel, K.H.; Finken, K.H. . Inst. fuer Plasmaphysik); Hulse, R.A.; Budny, R.V. . Plasma Physics Lab.)

    1990-01-01

    Many studies have shown the importance of the ratio {upsilon}{sub He}/{upsilon}{sub E} in determining the level of He ash accumulation in future reactor systems. Results of the first tokamak He removal experiments have been analysed, and a first estimate of the ratio {upsilon}{sub He}/{upsilon}{sub E} to be expected for future reactor systems has been made. The experiments were carried out for neutral beam heated plasmas in the TEXTOR tokamak, at KFA/Julich. Helium was injected both as a short puff and continuously, and subsequently extracted with the Advanced Limiter Test-II pump limiter. The rate at which the He density decays has been determined with absolutely calibrated charge exchange spectroscopy, and compared with theoretical models, using the Multiple Impurity Species Transport (MIST) code. An analysis of energy confinement has been made with PPPL TRANSP code, to distinguish beam from thermal confinement, especially for low density cases. The ALT-II pump limiter system is found to exhaust the He with maximum exhaust efficiency (8 pumps) of {approximately}8%. We find 1<{upsilon}{sub He}/{upsilon}{sub E}<3.3 for the database of cases analysed to date. Analysis with the ITER TETRA systems code shows that these values would be adequate to achieve the required He concentration with the present ITER divertor He extraction system.

  12. US ITER | About

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Systems EC Transmission Lines Electrical Network Exhaust IC Transmission Lines Magnet Pellet Injection Vacuum US Hardware Home > About US ITER > US Hardware US Hardware Contributions The ITER Tokamak will be the largest ever built, with a plasma volume of 840 cubic metres and a weight of 23,000 tons. The maximum plasma volume in current tokamaks is 100 cubic metres - achieved by both Europe's JET and Japan's JT-60. ITER members will share hardware procurements for the design and

  13. US ITER | Media Corner

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    3D printing yields advantages for US ITER engineers Desktop additive printers are changing the engineering design process 3D printing yields advantages for US ITER engineers Desktop additive printers are changing the engineering design process -Lynne Degitz Published March 11, 2014 A "toy"-sized, but accurately scaled, version of the ITER central solenoid (left) with one of the 18 toroidal field coils, printed on a desktop 3D printer. The pink oval represents the plasma. Notice the

  14. US ITER | Media Corner

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Building the heartbeat of ITER Building the heartbeat of ITER US ITER prepares for the fabrication of the international fusion reactor's central solenoid -Lynne Degitz Published February 24, 2014 Drive shaft gears General Atomics in San Diego, Calif., is overseeing the fabrication of the central solenoid, including the development of specialized tooling stations. This de-spooling tool-being developed by Tauring in Torino, Italy-will become part of the part of the conductor winding station at GA.

  15. US ITER | Media Corner

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    ORNL's Fusion Pellet Fueling Lab Innovations Support US ITER Systems ORNL's Fusion Pellet Fueling Lab Innovations Support US ITER Systems -Agatha Bardoel Published January 3, 2012 UT Magnet Lab Steve Combs holds target materials for evaluating disruption mitigation pellet size.Photo: US ITER/ORNL Oak Ridge National Laboratory's Fusion Pellet Fueling Lab has been at the center of design and testing of plasma fueling systems for tokamak research applications for decades. Since the mid-1970s, lab

  16. US ITER | Media Corner

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    US ITER high-performance pellet injection system advances to next stage US ITER high-performance pellet injection system advances to next stage Preparation is underway for full-scale prototype testing -Lynne Degitz Published September 16, 2013 Drive shaft gears The Oak Ridge National Laboratory-developed pellet injector is installed on the DIII-D tokamak for fueling and plasma edge control experiments. Photo: US ITER/ORNL Researchers at Oak Ridge National Laboratory developed a continuous

  17. What is ITER

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    ITER? ITER is a large international fusion experiment aimed at demonstrating the scientific and technological feasibility of fusion energy. ITER (Latin for "the way") will play a crit- ical role advancing the worldwide availability of energy from fusion - the power source of the sun and the stars. To produce practical amounts of fusion power on earth, heavy forms of hydrogen are joined together at high tem- perature with an accompanying production of heat en- ergy. The fuel must be

  18. US ITER | About

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Maps Maps The maps below will help you find your way to the US ITER Project Office and around ORNL and Oak Ridge. They are all provided in PDF format unless noted. ITER - Oak Ridge Office (Google Maps) ITER - Route from Knoxville McGhee-Tyson Airport ORNL Visitors Center Oak Ridge Oak Ridge/Knoxville to Visitor Center Oak Ridge Area/Knoxville Area Route from Knoxville McGhee-Tyson Airport to Oak Ridge ORNL Main Campus (close-up)

  19. US ITER | Media Corner

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Testing Central Solenoid Structural Integrity Testing Central Solenoid Structural Integrity Key steps forward for US ITER magnet efforts -Agatha Bardoel Published October 7, 2011 Vacuum Pressure Impregnation Vessel The vacuum pressure impregnation vessel will be used in testing methods for sealing and insulating ITER magnet modules. Photo: University of Tennessee Engineers and scientists at US ITER currently working on magnet projects have several key testing benchmarks over the next few months.

  20. US ITER | Contact Us

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    US Key Contact Key Contact Mark Uhran Communications Manager 865-574-8381 ITER International Department of Energy Office of Science Oak Ridge National Laboratory Princeton Plasma...

  1. What is ITER

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    facility, ITER will allow scientists to study reactor-scale burning plasmas and explore technical challenges related to the development of a power- producing fusion reactor. ...

  2. US ITER | Media Corner

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    test bed ring will load ITER transmission lines with up to 6 megawatts New test bed ring will load ITER transmission lines with up to 6 megawatts -Agatha Bardoel Published April 30, 2012 US ITER Toridal Field Coil Conductor The ion cyclotron resonance ring test stand at Oak Ridge National Laboratory's Energy Systems Test Complex. New test bed ring will load ITER transmission lines with up to 6 megawatts 'This is roughly a factor of 3 higher than any RF transmission line ever used in fusion

  3. US ITER | Media Corner

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Life-size Mock-Up Helps R&D Staff Get a Feel for the Scale of ITER Life-size Mock-Up Helps R&D Staff Get a Feel for the Scale of ITER -Agatha Bardoel Published October 7, 2011 A Mockup of the Central Solenoid Module A mockup of the central solenoid module will help the magnet team identify issues relevant for construction, installation, and maintenance. Photo: US ITER/ORNL At the University of Tennessee Magnet Development Lab, a full-scale wooden mock-up of a single ITER central solenoid

  4. US ITER | Doing Business

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    International: Business Opportunities with Other International Partners International: Business Opportunities with Other International Partners European Union The European Union maintains a website with additional ITER Business Opportunities. ITER International Department of Energy Office of Science Oak Ridge National Laboratory Princeton Plasma Physics Laboratory Savannah River National Laboratory Last updated: 06/25/2015

  5. US ITER | Media Corner

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    6 News Archive: 2006 Is Nuclear Fusion Possible? [Energy Central, December 4, 2006] ORNL Plays Key Part in Fusion Deal [ORNL Neutron Science Division, November 22, 2006] US ITER Project Completes Management Team [ORNL News Release, August 17, 2006] US ITER Project Office, a partnership of Princeton Plasma Physics Laboratory and Oak Ridge National Laboratory, relocating to ORNL [ORNL News Release, February 1, 2006

  6. Preconditioned Iterative Solver

    Energy Science and Technology Software Center (OSTI)

    2002-08-01

    AztecOO contains a collection of preconditioned iterative methods for the solution of sparse linear systems of equations. In addition to providing many of the common algebraic preconditioners and basic iterative methods, AztecOO can be easily extended to interact with user-provided preconditioners and matrix operators.

  7. Current generation by helicons and LH waves in modern tokamaks and reactors FNSF-AT, ITER and DEMO. Scenarios, modeling and antennae

    SciTech Connect (OSTI)

    Vdovin, V.

    2014-02-12

    The Innovative concept and 3D full wave code modeling Off-axis current drive by RF waves in large scale tokamaks, reactors FNSF-AT, ITER and DEMO for steady state operation with high efficiency was proposed [1] to overcome problems well known for LH method [2]. The scheme uses the helicons radiation (fast magnetosonic waves at high (20–40) IC frequency harmonics) at frequencies of 500–1000 MHz, propagating in the outer regions of the plasmas with a rotational transform. It is expected that the current generated by Helicons will help to have regimes with negative magnetic shear and internal transport barrier to ensure stability at high normalized plasma pressure β{sub N} > 3 (the so-called Advanced scenarios) of interest for FNSF and the commercial reactor. Modeling with full wave three-dimensional codes PSTELION and STELEC2 showed flexible control of the current profile in the reactor plasmas of ITER, FNSF-AT and DEMO [2,3], using multiple frequencies, the positions of the antennae and toroidal waves slow down. Also presented are the results of simulations of current generation by helicons in tokamaks DIII-D, T-15MD and JT-60SA [3]. In DEMO and Power Plant antenna is strongly simplified, being some analoge of mirrors based ECRF launcher, as will be shown. For spherical tokamaks the Helicons excitation scheme does not provide efficient Off-axis CD profile flexibility due to strong coupling of helicons with O-mode, also through the boundary conditions in low aspect machines, and intrinsic large amount of trapped electrons, as is shown by STELION modeling for the NSTX tokamak. Brief history of Helicons experimental and modeling exploration in straight plasmas, tokamaks and tokamak based fusion Reactors projects is given, including planned joint DIII-D – Kurchatov Institute experiment on helicons CD [1].

  8. US ITER | Media Corner

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Winding of the central solenoid mock-up module has begun Winding of the central solenoid mock-up module has begun -Lynne Degitz Published November 17, 2014 The first part of the central solenoid winding station is a de-spooler, shown here unwinding material for the mock-up coil. Photo: US ITER. The first part of the central solenoid winding station is a de-spooler, shown here unwinding material for the mock-up coil. Photo: US ITER . At the heart of the ITER international fusion reactor-scale

  9. INSIDE: ITER Site Progress

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Industry Monaco/ITER Postdoctoral Fellowship Program Upcoming Events US Researchers Parse Complex Plasma Issues From "Snowballs in Hell" to "Burping the Baby" - by Agatha Bardoel The design, testing, and manufacture of a pellet injection system is one of the key contributions of the United States to ITER. Physicist David Rasmussen serves as the lead for US ITER's fueling team and as a group leader in the Fusion Energy Division at Oak Ridge National Laboratory. He points out

  10. US ITER | Jobs

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Nicolai Martovetsky US ITER Magnet Systems R&D Manager and Chief Engineer Tell us about your background Nicolai Martovetsky Nicolai Martovetsky I earned my Ph.D. at the Kurchatov Institute of Atomic Energy in Moscow, in 1985. I am a mechanical engineer. What were you doing before you came to US ITER? Before coming to US ITER, I was a research scientist at Lawrence Livermore National Laboratory (LLNL), in Livermore, Calif. I am currently on assignment here at Oak Ridge National Laboratory,

  11. US ITER | Contact Us

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Staff Directory Staff Directory Lookup Fields Last Name Institution Submit Reset ITER International Department of Energy Office of Science Oak Ridge National Laboratory Princeton Plasma Physics Laboratory Savannah River National Laboratory Last updated: 03/08/2016

  12. INSIDE: ITER Site Progress

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    of all 400 kV substation equipment and all 22 kV switchgear. 2 Four US-supplied HV transformers were the first plant components installed at the ITER site in October 2015. Photo:...

  13. US ITER - Why Fusion?

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Educational Resources Fusion Educational Resources DOE Office of Science Fusion Energy Programs Education Links FuseNet: The European Fusion Education Network General Atomics Fusion Education PPPL Science Education Program PPPL FusEdWeb Educational Outreach: US ITER staff members are available for presentations on fusion energy and the ITER project to technical, civic, community, and student groups. To make arrangements for a speaker, please contact Mark Uhran, Communications Manager,

  14. US ITER | Doing Business

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    ITER International Organization Competitive Task Agreements International Organization Competitive Task Agreements There are currently no requests for proposals or expressions of interest. If there are any questions regarding the task agreements, please contact Wayne Steffey (865-574-8364) or Mary Jane Maelzer (865-574-0358). ITER International Department of Energy Office of Science Oak Ridge National Laboratory Princeton Plasma Physics Laboratory Savannah River National Laboratory Last updated:

  15. INSIDE: ITER Site Progress

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Continued on page 8 INSIDE: ITER Site Progress View from DOE US Systems Update Engaging Industry, Universities and Labs Upcoming Events Disruption Mitigation Researchers Investigate Design Options ITER, the world's first reactor-scale fusion machine, will have a plasma volume more than 10 times that of the next largest tokamak, JET. Plasma disruptions that can occur in a tokamak when the plasma becomes unstable can potentially damage plasma-facing surfaces of the machine. To lessen the impact of

  16. US ITER | Media Corner

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Fusion diagnostics heat up across the US Fusion diagnostics heat up across the US Teams are developing tools to monitor and control ITER plasma -Lynne Degitz October 22, 2015 ITER, the world's largest tokamak now under construction in France, will have over 60 diagnostic systems installed to enable plasma control, optimize plasma performance, and support machine protection¬. Princeton Plasma Physics Laboratory and Oak Ridge National Laboratory, in collaboration with industry and universities,

  17. US ITER | About

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    EC Transmission Lines Electrical Network Exhaust IC Transmission Lines Magnet Pellet Injection Vacuum US Hardware Home > About US ITER > US Hardware > Toroidal Field (TF) Magnets Central Solenoid (CS) (WBS 1.1.1) Fact Sheet Central Solenoid Highlighted in pink: The central solenoid, or "backbone" of the ITER Magnet System. The US is responsible for 100% of the central solenoid (CS) magnet, including design, R&D, fabrication of 7 CS modules using supplied conductor (from

  18. US ITER | About

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Tokamak Cooling Water System Tokamak Cooling Water System (WBS 1.2.1) Fact Sheet Cooling Water Systems Image Highlighted in pink: ITER Tokamak Cooling Water System. The US is responsible for 100% of the design, engineering, and procurement of the Tokamak Cooling Water System (TCWS). ITER's fusion power will reach 500 MW during the deuterium-tritium inductive plasma operation with an energy input of only 50 MW, yielding an energy multiplication factor of 10. Heat will be transferred by the

  19. US ITER | About

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Tokamak Exhaust Processing Systems Tokamak Exhaust Processing System (WBS 1.3.2) FactSheet Exhaust Process Image The ITER tokamak exhaust process design. The US is responsible for 100% of the final design, fabrication, assembly, testing, and shipment of the Tokamak Exhaust Processing (TEP) system. This effort is under way at Savannah River National Laboratory, in partnership with Los Alamos National Laboratory. ITER will require the processing of an unprecedented rate of hydrogen isotopes. To

  20. US ITER | About

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Pellet Injection System Pellet Injection System (WBS 1.3.1) Fact Sheet ITER Vacuum Vessle and Cryostat Image Highlighted in pink: Vacuum Pumping and Pellet Injection Systems. The US will contribute 100% towards the fueling and edge localized mode mitigation system. To: The US will contribute 100% towards the pellet injection system for fueling and edge localized mode mitigation. ITER will require significant fueling capability to operate at high density for long durations. Pellet injection

  1. US ITER | About

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Toroidal Field (TF) Magnets Toroidal Field (TF) Magnets (WBS 1.1.1) Fact Sheet TF Coil Highlighted in pink: One of the 18 toroidal field magents around the torus of the ITER tokamak design. The US will contribute 8% of the toroidal field (TF) coil conductors. The ITER Organization is responsible for the conductor design which is released for fabrication. Japan, the European Union, the Russian Federation, Korea, and China are also contributing TF conductor. The 18 toroidal field coils produce a

  2. US ITER | About

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Vacuum Auxiliary Systems Vacuum Auxiliary Systems (WBS 1.3.1) Fact Sheet ITER Vacuum Vessle and Cryostat Image Highlighted in pink: Vacuum Pumping and Pellet Injection Systems. The US will contribute 100% towards the roughing pumps and vacuum auxiliary system. The ITER tokamak, cryostat, and auxiliary vacuum chambers must be evacuated prior to and during operations. The roughing pump system exhausts the torus and neutral beam injector cryopumps, service vacuum, and cryostat. This system will

  3. US ITER | Jobs

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Kevin Chan US ITER Toroidal Field Coil Conductor Project Engineer Tell us about your background Kevin Chan Kevin Chan I was born in Pittsburgh, Pennsylvania and I am a mechanical engineer. What were you doing before you came to US ITER? From 1996-2003, I was maintenance supervisor, project planner, project engineer, and area manager for AK Steel, in Middletown, Ohio, a company that produces flat-rolled steel and aluminum coated stainless steel for the automotive, appliance, construction, and

  4. PPPL--2702 Power Radiated from ITER

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    702 " Power Radiated from ITER and CIT by Impurities D E ~ O 014715 J. Cummings, S. A. Cohen, R Hulse, D. E. Post, M. H. Redi and J. Perkinst Princeton Plasma Physics Laboratory Princeton University, Rinceton, NJ 08543 Abstract The MIST code has been used to model impurity radiation from the edge and core plasmas in ITER and CIT. A broad range of parameters have been varied, including Zeff, impurity species, impurity transport coefficients, and plasma temperature and density profiles,

  5. US ITER | Media Corner

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    US ITER ships 30,000 pounds of magnet system hardware to Europe US ITER ships 30,000 pounds of magnet system hardware to Europe An 800-meter length of sample toroidal field conductor is en route to La Spezia, Italy -Lynne Degitz Published June 9, 2014 The 800-meter sample toroidal field conductor was transferred to a container ship at the port of Charleston, S.C., on May 28, 2014 for its voyage to La Spezia, Italy. The 800-meter sample toroidal field conductor was transferred to a container ship

  6. US ITER | Jobs

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Frank Casella US ITER Quality Assurance, Environmental, Safety and Health and Licensing Support Manager Tell us about your background Frank Casella Frank Casella I was born in Brooklyn, New York, but grew up in northern New Hampshire, where I went to high school. I attended Colgate University and then joined the Navy. I trained for the nuclear power program and specifically for nuclear submarines, and then spent four years on a nuclear sub. What were you doing before you came to US ITER? After I

  7. US ITER | Jobs

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Suzanne Herron US ITER Deputy Project Manager Tell us about your background Suzanne Herron Suzanne Herron I have a BS in mathematics, a master's degree in Industrial and Systems Engineering and am a certified project manager. I was born in Ohio. However, I have lived and worked in Tennessee for the past 25 years. What were you doing before you came to US ITER? I have had a variety of experiences in my career. I started out in Ohio, working on the Gaseous Diffusion Program for the enrichment of

  8. US ITER | Media Corner

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    In Jacob's Room at US ITER Fusion Comes to the Secret City Published June 20, 2011 The USIPO joined ORNL neighbor Spallation Neutron Source to offer an interactive "science village" at the annual Secret City Festival in Oak Ridge, Tennessee on June 17-18, 2011. This is the first year that current science projects hosted at Oak Ridge have been represented at the festival. Over 1000 visitors toured the exhibits and learned more about fusion, ITER progress, and other cutting edge research

  9. ITER Fusion Energy

    ScienceCinema (OSTI)

    Dr. Norbert Holtkamp

    2010-01-08

    ITER (in Latin ?the way?) is designed to demonstrate the scientific and technological feasibility of fusion energy. Fusion is the process by which two light atomic nuclei combine to form a heavier over one and thus release energy. In the fusion process two isotopes of hydrogen ? deuterium and tritium ? fuse together to form a helium atom and a neutron. Thus fusion could provide large scale energy production without greenhouse effects; essentially limitless fuel would be available all over the world. The principal goals of ITER are to generate 500 megawatts of fusion power for periods of 300 to 500 seconds with a fusion power multiplication factor, Q, of at least 10. Q ? 10 (input power 50 MW / output power 500 MW). The ITER Organization was officially established in Cadarache, France, on 24 October 2007. The seven members engaged in the project ? China, the European Union, India, Japan, Korea, Russia and the United States ? represent more than half the world?s population. The costs for ITER are shared by the seven members. The cost for the construction will be approximately 5.5 billion Euros, a similar amount is foreseen for the twenty-year phase of operation and the subsequent decommissioning.

  10. Nuclear Forensic Inferences Using Iterative Multidimensional Statistics

    SciTech Connect (OSTI)

    Robel, M; Kristo, M J; Heller, M A

    2009-06-09

    Nuclear forensics involves the analysis of interdicted nuclear material for specific material characteristics (referred to as 'signatures') that imply specific geographical locations, production processes, culprit intentions, etc. Predictive signatures rely on expert knowledge of physics, chemistry, and engineering to develop inferences from these material characteristics. Comparative signatures, on the other hand, rely on comparison of the material characteristics of the interdicted sample (the 'questioned sample' in FBI parlance) with those of a set of known samples. In the ideal case, the set of known samples would be a comprehensive nuclear forensics database, a database which does not currently exist. In fact, our ability to analyze interdicted samples and produce an extensive list of precise materials characteristics far exceeds our ability to interpret the results. Therefore, as we seek to develop the extensive databases necessary for nuclear forensics, we must also develop the methods necessary to produce the necessary inferences from comparison of our analytical results with these large, multidimensional sets of data. In the work reported here, we used a large, multidimensional dataset of results from quality control analyses of uranium ore concentrate (UOC, sometimes called 'yellowcake'). We have found that traditional multidimensional techniques, such as principal components analysis (PCA), are especially useful for understanding such datasets and drawing relevant conclusions. In particular, we have developed an iterative partial least squares-discriminant analysis (PLS-DA) procedure that has proven especially adept at identifying the production location of unknown UOC samples. By removing classes which fell far outside the initial decision boundary, and then rebuilding the PLS-DA model, we have consistently produced better and more definitive attributions than with a single pass classification approach. Performance of the iterative PLS-DA method compared favorably to that of classification and regression tree (CART) and k nearest neighbor (KNN) algorithms, with the best combination of accuracy and robustness, as tested by classifying samples measured independently in our laboratories against the vendor QC based reference set.

  11. ITER | Princeton Plasma Physics Lab

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    ITER Subscribe to RSS - ITER ITER is a large international fusion experiment aimed at demonstrating the scientific and technological feasibility of fusion energy. ITER (Latin for "the way") will play a critical role advancing the worldwide availability of energy from fusion - the power source of the sun and the stars. To produce practical amounts of fusion power on earth, heavy forms of hydrogen are joined together at high temperature with an accompanying production of heat energy. The

  12. US ITER | About

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Information Visitor Information Welcome to East Tennessee, Oak Ridge National Laboratory (ORNL), and the U.S. ITER Project Office. This is a scenic and geographically diverse area with much to offer. Economic opportunities are evolving rapidly, and academic opportunities are abundant. East Tennessee is an area rich with friendly people, cultural experiences, and unlimited outdoor activities The purpose of this site is to help you acquire basic information and contacts that will enhance your stay

  13. US ITER | Doing Business

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    International: Calls for Nominations and Calls for Expertise International Opportunities For questions about calls for nominations or calls for expertise, please contact Terri Cleveland at clevelandtd@ornl.gov or 865-574-1022. If you are a US company and wish to express an interest in participating in a bid process for one of the above International ITER Organization requirements, please review USIPO's Export Control Awareness document. If you agree to follow the guidance provided in this

  14. US ITER | Media Corner

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Cryogenic deuterium machine gun corrals edgy plasma Cryogenic deuterium machine gun corrals edgy plasma -Agatha Bardoel Published May 3, 2012 Cryogenic deuterium machine gun Internal image of the three-barrel repeating pneumatic deuterium pellet injector used on DIII-D for pellet ELM pacing experiments. Photo: US ITER/ORNL Using a cryogenic deuterium pellet injector installed on the DIII-D tokamak operated for the Department of Energy Office of Science by General Atomics in San Diego, ORNL

  15. US ITER | Media Corner

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Disruption mitigation researchers investigate design options Disruption mitigation researchers investigate design options -Lynne Degitz Published January 4, 2013 ITER, the world's first reactor-scale fusion machine, will have a plasma volume more than 10 times that of the next largest tokamak, JET. Plasma disruptions that can occur in a tokamak when the plasma becomes unstable can potentially damage plasma-facing surfaces of the machine. To lessen the impact of high energy plasma disruptions, US

  16. US ITER | Media Corner

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    7 News Archive: 2007 SRNL to help in study of fusion [Aiken Standard, January 16, 2007] United States-Japan Cooperation on Energy Security [Media Newswire, January 11, 2007] ORNL researchers, supercomputer have large roles in DOE projects [ORNL News Release, January 9, 2007] SNS completion highlights year of ORNL achievements [The Oak Ridger, January 4, 2007] US and German Leaders Explore Climate Cooperation [Environment News Service, January 4, 2007] Head of US ITER project named IEEE Fellow

  17. US ITER | Media Corner

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    8 News Archive: 2008 New insights on fusion power [PhysOrg.com, December 3, 2008] Nuclear Fusion Moves One Step Closer [LiveScience.com, December 3, 2008] NRC Committee Reviews DOE Fusion Plan [SEA, November 19, 2008] ORNL's stainless steel attracts global interest [Knoxville News Sentinel, November 4, 2008] Scientists develop high-performance steel for ITER [The Oak Ridger, November 2, 2008] Can Engineers Achieve the Holy Grail of Energy: Infinite and Clean? [Discover Magazine, October 6, 2008]

  18. US ITER | About

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Electron Cyclotron Heating Transmission Lines Electron Cyclotron Heating Transmission Lines (WBS 1.5.2) Fact Sheet Electron Cyclotron Heating System Image Highlighted in pink: ITER Electron Cyclotron Heating Transmission Lines. The US is responsible for 88% of the electron cyclotron transmission lines, including research and development (with Oak Ridge National Laboratory and Massachusetts Institute of Technology), design, fabrication, and interfaces. The IO is responsible for installing the

  19. US ITER | About

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Ion Cyclotron Heating Transmission Lines Ion Cyclotron Heating Transmission Lines (WBS 1.5.1) Fact Sheet ICH Image Highlighted in pink: ITER Ion Cyclotron Heating Transmission Lines. The US is responsible for 88% of the ion cyclotron transmission lines, including research and development (with Oak Ridge National Laboratory and Princeton Plasma Physics Laboratory), design, fabrication, and interfaces. The IO is responsible for installing the ion cyclotron transmission lines (12%). The ion

  20. US ITER | About

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Steady-State Electrical Network Steady State Electrical Network (WBS 1.4.1) Fact Sheet The US contributes 75% of the equipment required for the Steady-State Electrical Network (SSEN), excluding cables and emergency power. The European Union contributes the remaining equipment and is also responsible for the design and installation of the system. The Steady-State Electrical Network is an AC power substation and distribution system that supplies electrical power to all ITER conventional systems

  1. US ITER | About

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Transportation Transportation Taxi and limousine service is available from the Knoxville airport to Oak Ridge and Knoxville hotels. Because a taxi may not be available when you want it and because you will need to provide your own transportation to and from US ITER. A rental car is suggested for short stays. A driver's license, credit card, and proof of insurance is required by man driving car rental car agencies. An international driver's license is required for foreign national visitors.

  2. US ITER | Jobs

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Kelli Kizer Subcontract Administrator Tell us about your background Kelli Kizer Kelli Kizer I was born in Knoxville, Tennessee, attended Lenoir City High School, then studied and graduated from the University of Tennessee, Knoxville (UTK) with a BS in Business Administration. What were you doing before you came to US ITER? When I was a sophomore at UTK, I began to intern during summers at the Oak Ridge National Laboratory. Upon graduating, I began working in the Environmental Restoration

  3. US ITER | Media Corner

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Videos from the Around the World of Fusion Fusion Power: Quest for the Ultimate Energy Source An interview with US fusion researcher Steve Dean, Founder of Fusion Power Associates. [August 18, 2013, interview by Tim Truett] Fusion Energy Production by Neutral Particle Injection This visualization demonstrates how the ITER reactor will create a burning plasma. [Sept. 28, 2012, National Center for Computational Sciences at Oak Ridge National Laboratory, 4:40] An earlier version of this animation

  4. Iterative reconstruction of magnetic induction using Lorentz...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Iterative reconstruction of magnetic induction using Lorentz transmission electron tomography Title Iterative reconstruction of magnetic induction using Lorentz transmission...

  5. ETR/ITER systems code

    SciTech Connect (OSTI)

    Barr, W.L.; Bathke, C.G.; Brooks, J.N.; Bulmer, R.H.; Busigin, A.; DuBois, P.F.; Fenstermacher, M.E.; Fink, J.; Finn, P.A.; Galambos, J.D.; Gohar, Y.; Gorker, G.E.; Haines, J.R.; Hassanein, A.M.; Hicks, D.R.; Ho, S.K.; Kalsi, S.S.; Kalyanam, K.M.; Kerns, J.A.; Lee, J.D.; Miller, J.R.; Miller, R.L.; Myall, J.O.; Peng, Y-K.M.; Perkins, L.J.; Spampinato, P.T.; Strickler, D.J.; Thomson, S.L.; Wagner, C.E.; Willms, R.S.; Reid, R.L.

    1988-04-01

    A tokamak systems code capable of modeling experimental test reactors has been developed and is described in this document. The code, named TETRA (for Tokamak Engineering Test Reactor Analysis), consists of a series of modules, each describing a tokamak system or component, controlled by an optimizer/driver. This code development was a national effort in that the modules were contributed by members of the fusion community and integrated into a code by the Fusion Engineering Design Center. The code has been checked out on the Cray computers at the National Magnetic Fusion Energy Computing Center and has satisfactorily simulated the Tokamak Ignition/Burn Experimental Reactor II (TIBER) design. A feature of this code is the ability to perform optimization studies through the use of a numerical software package, which iterates prescribed variables to satisfy a set of prescribed equations or constraints. This code will be used to perform sensitivity studies for the proposed International Thermonuclear Experimental Reactor (ITER). 22 figs., 29 tabs.

  6. US ITER | Doing Business

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    US Business Opportunities US Business Opportunities Upcoming US ITER Procurements WBS Description RFP Projected Date Projected Award Date $ Estimate POC WBS 1.1.1.2 Multi Jack Bolt Tensioners June 2016 August 2016 >$1M Kelly West (luckettwestk@ornl.gov) 865-576-6880 WBS 1.1.1.2 Lead Support Brackets/Manifold Platforms/Module Alignment System June 2016 August 2016 >$500K Kelly West (luckettwestk@ornl.gov) 865-576-6880 WBS 1.1.1.2 Fabrication of Lower Components Note: CS structure lower

  7. US ITER | Why Fusion?

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Why Fusion? US Fusion Research Educational Resources Why Fusion? Home > Why Fusion? What is Fusion? Fusion is a key element in long-term US energy plans. ITER will allow scientists to explore the physics of a burning plasma at energy densities close to that of a commercial power plant. This is a critical step towards producing and delivering electricity from fusion to the grid. Nuclear fusion occurs naturally in stars, like our sun. When hydrogen gets hot enough, the process of fusion

  8. US ITER | Media Corner

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    From Snowballs in Hell to Burping the Baby From "Snowballs in Hell" to "Burping the Baby" US Researchers Parse Complex Plasma Issues -Agatha Bardoel Published October 31, 2011 Vacuum Pressure Impregnation Vessel A large (+16 mm) pellet is undergoing testing for ITER disruption mitigation. In this photo, the pellet, on the left, is exiting the guide tube just before hitting a simple target plate. It will shatter once it hits the plate. (Photo: Combs, ORNL) Heated to extreme

  9. SciDAC Center for Simulation of Wave-Plasma Interactions - Iterated Finite-Orbit Monte Carlo Simulations with Full-Wave Fields for Modeling Tokamak ICRF Wave Heating Experiments - Final Report

    SciTech Connect (OSTI)

    Choi, Myunghee; Chan, Vincent S.

    2014-02-28

    This final report describes the work performed under U.S. Department of Energy Cooperative Agreement DE-FC02-08ER54954 for the period April 1, 2011 through March 31, 2013. The goal of this project was to perform iterated finite-orbit Monte Carlo simulations with full-wall fields for modeling tokamak ICRF wave heating experiments. In year 1, the finite-orbit Monte-Carlo code ORBIT-RF and its iteration algorithms with the full-wave code AORSA were improved to enable systematical study of the factors responsible for the discrepancy in the simulated and the measured fast-ion FIDA signals in the DIII-D and NSTX ICRF fast-wave (FW) experiments. In year 2, ORBIT-RF was coupled to the TORIC full-wave code for a comparative study of ORBIT-RF/TORIC and ORBIT-RF/AORSA results in FW experiments.

  10. Pore scale modeling of reactive transport involved in geologic CO2 sequestration

    SciTech Connect (OSTI)

    Kang, Qinjin; Lichtner, Peter C; Viswanathan, Hari S; Abdel-fattah, Amr I

    2009-01-01

    We apply a multi-component reactive transport lattice Boltzmann model developed in previolls studies to modeling the injection of a C02 saturated brine into various porous media structures at temperature T=25 and 80 C. The porous media are originally consisted of calcite. A chemical system consisting of Na+, Ca2+, Mg2+, H+, CO2(aq), and CI-is considered. The fluid flow, advection and diHusion of aqueous species, homogeneous reactions occurring in the bulk fluid, as weB as the dissolution of calcite and precipitation of dolomite are simulated at the pore scale. The effects of porous media structure on reactive transport are investigated. The results are compared with continuum scale modeling and the agreement and discrepancy are discussed. This work may shed some light on the fundamental physics occurring at the pore scale for reactive transport involved in geologic C02 sequestration.

  11. ITER | Princeton Plasma Physics Lab

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    fusion experiment aimed at demonstrating the scientific and technological feasibility of fusion energy. ITER (Latin for "the way") will play a critical role advancing...

  12. US Contributions to ITER Project

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Contributions to ITER Project 12/7/15 † = D etailee * M = M atrix * S /C = S ubcontractor * * = D ual C apacity 2

  13. BBC Video Looks at ITER | Princeton Plasma Physics Lab

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    BBC Video Looks at ITER American Fusion News Category: U.S. ITER Link: BBC Video Looks at ITER

  14. ITER Diagnostic First Wal

    SciTech Connect (OSTI)

    G. Douglas Loesser, et. al.

    2012-09-21

    The ITER Diagnostic Division is responsible for designing and procuring the First Wall Blankets that are mounted on the vacuum vessel port plugs at both the upper and equatorial levels This paper will discuss the effects of the diagnostic aperture shape and configuration on the coolant circuit design. The DFW design is driven in large part by the need to conform the coolant arrangement to a wide variety of diagnostic apertures combined with the more severe heating conditions at the surface facing the plasma, the first wall. At the first wall, a radiant heat flux of 35W/cm2 combines with approximate peak volumetric heating rates of 8W/cm3 (equatorial ports) and 5W/cm3 (upper ports). Here at the FW, a fast thermal response is desirable and leads to a thin element between the heat flux and coolant. This requirement is opposed by the wish for a thicker FW element to accommodate surface erosion and other off-normal plasma events.

  15. In-vessel tritium retention and removal in ITER

    SciTech Connect (OSTI)

    Federici, G.; Anderl, R.A.; Andrew, P.

    1998-06-01

    The International Thermonuclear Experimental Reactor (ITER) is envisioned to be the next major step in the world`s fusion program from the present generation of tokamaks and is designed to study fusion plasmas with a reactor relevant range of plasma parameters. During normal operation, it is expected that a fraction of the unburned tritium, that is used to routinely fuel the discharge, will be retained together with deuterium on the surfaces and in the bulk of the plasma facing materials (PFMs) surrounding the core and divertor plasma. The understanding of he basic retention mechanisms (physical and chemical) involved and their dependence upon plasma parameters and other relevant operation conditions is necessary for the accurate prediction of the amount of tritium retained at any given time in the ITER torus. Accurate estimates are essential to assess the radiological hazards associated with routine operation and with potential accident scenarios which may lead to mobilization of tritium that is not tenaciously held. Estimates are needed to establish the detritiation requirements for coolant water, to determine the plasma fueling and tritium supply requirements, and to establish the needed frequency and the procedures for tritium recovery and clean-up. The organization of this paper is as follows. Section 2 provides an overview of the design and operating conditions of the main components which define the plasma boundary of ITER. Section 3 reviews the erosion database and the results of recent relevant experiments conducted both in laboratory facilities and in tokamaks. These data provide the experimental basis and serve as an important benchmark for both model development (discussed in Section 4) and calculations (discussed in Section 5) that are required to predict tritium inventory build-up in ITER. Section 6 emphasizes the need to develop and test methods to remove the tritium from the codeposited C-based films and reviews the status and the prospects of the most attractive techniques. Section 7 identifies the unresolved issues and provides some recommendations on potential R and D avenues for their resolution. Finally, a summary is provided in Section 8.

  16. Travel Requirements - ITER (June 2014

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Travel Requirements - ITER (June 2014) Prior to any travel under this subcontract, the Seller shall submit their request to travel with the following information to the Technical Project Officer (TPO) for approval, with a copy to the identified US ITER Project Office Travel Administrative Coordinator (TAC), via email: name of traveler as it appears on passport; e-mail address of traveler; dates of travel; purpose of travel; business city; date business begins; and date business ends. The TAC for

  17. ODE System Solver W. Krylov Iteration & Rootfinding

    Energy Science and Technology Software Center (OSTI)

    1991-09-09

    LSODKR is a new initial value ODE solver for stiff and nonstiff systems. It is a variant of the LSODPK and LSODE solvers, intended mainly for large stiff systems. The main differences between LSODKR and LSODE are the following: (a) for stiff systems, LSODKR uses a corrector iteration composed of Newton iteration and one of four preconditioned Krylov subspace iteration methods. The user must supply routines for the preconditioning operations, (b) Within the corrector iteration,more » LSODKR does automatic switching between functional (fixpoint) iteration and modified Newton iteration, (c) LSODKR includes the ability to find roots of given functions of the solution during the integration.« less

  18. ODE System Solver W. Krylov Iteration & Rootfinding

    Energy Science and Technology Software Center (OSTI)

    1991-09-09

    LSODKR is a new initial value ODE solver for stiff and nonstiff systems. It is a variant of the LSODPK and LSODE solvers, intended mainly for large stiff systems. The main differences between LSODKR and LSODE are the following: (a) for stiff systems, LSODKR uses a corrector iteration composed of Newton iteration and one of four preconditioned Krylov subspace iteration methods. The user must supply routines for the preconditioning operations, (b) Within the corrector iteration,moreLSODKR does automatic switching between functional (fixpoint) iteration and modified Newton iteration, (c) LSODKR includes the ability to find roots of given functions of the solution during the integration.less

  19. RIGHT OF ACCESS BY OTHERS - ITER (December 2013

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    RIGHT OF ACCESS BY OTHERS - ITER (December 2013) In order to ensure the quality and fitness of components and systems procured for ITER, the Company, ITER International...

  20. Microsoft Word - ex15-ITER-sept10.doc

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    - ITER UT-B Contracts Div Sept 2010 Page 1 of 1 ex15-ITER-sept10.doc Exhibit 15-ITER Ref: FAR 52.227-17 RIGHTS IN DATA SPECIAL WORKS ITER (Sept 2010) (a) Definitions. (1)...

  1. Electromagnetic analysis of forces and torques on the ITER shield modules due to plasma disruption.

    SciTech Connect (OSTI)

    Kotulski, Joseph Daniel; Coats, Rebecca Sue; Pasik, Michael Francis; Ulrickson, Michael Andrew

    2009-06-01

    An electromagnetic analysis is performed on the ITER shield modules under different plasma disruption scenarios using the OPERA-3d software. The modeling procedure is explained, electromagnetic torques are presented, and results of the modeling are discussed.

  2. Identification of Export Control Classification Number - ITER

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Identification of Export Control Classification Number - ITER (April 2012) As the "Shipper of Record" please provide the appropriate Export Control Classification Number (ECCN) for the products (equipment, components and/or materials) and if applicable the nonproprietary associated installation/maintenance documentation that will be shipped from the United States to the ITER International Organization in Cadarache, France or to ITER Members worldwide on behalf of the Company. In rare

  3. Iterative reconstruction of magnetic induction using Lorentz...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    induction of a nanostructure. This allows for implementing the reconstruction as a linear algebra problem such that various iterative algebraic reconstruction methods can be...

  4. Identification of Export Control Classification Number - ITER

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Identification of Export Control Classification Number - ITER (April 2012) As the "Shipper of Record" please provide the appropriate Export Control Classification Number (ECCN) for...

  5. Looking northeast over the ITER construction site

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    significant approval of a project baseline by the ITER Council, to the appointment ... (IO) - unanimously approved the project baseline as presented by the IO. The baseline ...

  6. Research at ITER towards DEMO: Specific reactor diagnostic studies to be carried out on ITER

    SciTech Connect (OSTI)

    Krasilnikov, A. V.; Kaschuck, Y. A.; Vershkov, V. A.; Petrov, A. A.; Petrov, V. G.; Tugarinov, S. N. [Institution Project center ITER, Moscow (Russian Federation)

    2014-08-21

    In ITER diagnostics will operate in the very hard radiation environment of fusion reactor. Extensive technology studies are carried out during development of the ITER diagnostics and procedures of their calibration and remote handling. Results of these studies and practical application of the developed diagnostics on ITER will provide the direct input to DEMO diagnostic development. The list of DEMO measurement requirements and diagnostics will be determined during ITER experiments on the bases of ITER plasma physics results and success of particular diagnostic application in reactor-like ITER plasma. Majority of ITER diagnostic already passed the conceptual design phase and represent the state of the art in fusion plasma diagnostic development. The number of related to DEMO results of ITER diagnostic studies such as design and prototype manufacture of: neutron and ?ray diagnostics, neutral particle analyzers, optical spectroscopy including first mirror protection and cleaning technics, reflectometry, refractometry, tritium retention measurements etc. are discussed.

  7. Models Datasets

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    iteration by iteration. RevSim is an Excel 2010 based model. Much of the logic is VBA code (Visual Basic for Applications); the user does not need to know VBA to run the...

  8. Genome-Wide Identification and 3D Modeling of Proteins involved in DNA Damage Recognition and Repair (Final Report)

    SciTech Connect (OSTI)

    Ruben A. Abagyan, PhD

    2004-04-15

    OAK-B135 DNA Damage Recognition and Repair (DDR and R) proteins play a critical role in cellular responses to low-dose radiation and are associated with cancer. the authors have performed a systematic, genome-wide computational analysis of genomic data for human genes involved in the DDR and R process. The significant achievements of this project include: (1) Construction of the computational pipeline for searching DDR and R genes, building and validation of 3D models of proteins involved in DDR and R; (2) Functional and structural annotation of the 3D models and generation of comprehensive lists of suggested knock-out mutations; (3) Important improvement of macromolecular docking technology and its application to predict the DNA-Protein complex conformation; (4) Development of a new algorithm for improved analysis of high-density oligonucleotide arrays for gene expression profiling; (5) Construction and maintenance of the DNA Damage Recognition and Repair Database; and (6) Producing 14 research papers (10 published and 4 in preparation).

  9. Genome-Wide Identification and 3D Modeling of Proteins involved in DNA Damage Recognition and Repair (Final Report)

    SciTech Connect (OSTI)

    Abagyan, Ruben; An, Jianghong

    2005-08-12

    DNA Damage Recognition and Repair (DDR&R) proteins play a critical role in cellular responses to low-dose radiation and are associated with cancer. We have performed a systematic, genome-wide computational analysis of genomic data for human genes involved in the DDR&R process. The significant achievements of this project include: 1) Construction of the computational pipeline for searching DDR&R genes, building and validation of 3D models of proteins involved in DDR&R; 2) Functional and structural annotation of the 3D models and generation of comprehensive lists of suggested knock-out mutations; and the development of a method to predict the effects of mutations. Large scale testing of technology to identify novel small binding pockets in protein structures leading to new DDRR inhibitor strategies 3) Improvements of macromolecular docking technology (see the CAPRI 1-3 and 4-5 results) 4) Development of a new algorithm for improved analysis of high-density oligonucleotide arrays for gene expression profiling; 5) Construction and maintenance of the DNA Damage Recognition and Repair Database; 6) Producing 15 research papers (12 published and 3 in preparation).

  10. Neutronics at Wisconsin, ORNL advances ITER shielding and international

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    collaboration | Princeton Plasma Physics Lab Neutronics at Wisconsin, ORNL advances ITER shielding and international collaboration American Fusion News Category: U.S. ITER Link: Neutronics at Wisconsin, ORNL advances ITER shielding and international collaboration

  11. The ITER Project: International Collaboration to Demonstrate Nuclear Fusion

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    | Princeton Plasma Physics Lab The ITER Project: International Collaboration to Demonstrate Nuclear Fusion American Fusion News Category: U.S. ITER Link: The ITER Project: International Collaboration to Demonstrate Nuclear Fusion

  12. ITER Generic Diagnostic Upper Port Plug Nuclear Heating and Personnel Dose Rate Assesment

    SciTech Connect (OSTI)

    Russell E. Feder and Mahmoud Z. Youssef

    2009-01-28

    Neutronics analysis to find nuclear heating rates and personnel dose rates were conducted in support of the integration of diagnostics in to the ITER Upper Port Plugs. Simplified shielding models of the Visible-Infrared diagnostic and of a large aperture diagnostic were incorporated in to the ITER global CAD model. Results for these systems are representative of typical designs with maximum shielding and a small aperture (Vis-IR) and minimal shielding with a large aperture. The neutronics discrete-ordinates code ATTILA and SEVERIAN (the ATTILA parallel processing version) was used. Material properties and the 500 MW D-T volume source were taken from the ITER Brand Model MCNP benchmark model. A biased quadrature set equivelant to Sn=32 and a scattering degree of Pn=3 were used along with a 46-neutron and 21-gamma FENDL energy subgrouping. Total nuclear heating (neutron plug gamma heating) in the upper port plugs ranged between 380 and 350 kW for the Vis-IR and Large Aperture cases. The Large Aperture model exhibited lower total heating but much higher peak volumetric heating on the upper port plug structure. Personnel dose rates are calculated in a three step process involving a neutron-only transport calculation, the generation of activation volume sources at pre-defined time steps and finally gamma transport analyses are run for selected time steps. ANSI-ANS 6.1.1 1977 Flux-to-Dose conversion factors were used. Dose rates were evaluated for 1 full year of 500 MW DT operation which is comprised of 3000 1800-second pulses. After one year the machine is shut down for maintenance and personnel are permitted to access the diagnostic interspace after 2-weeks if dose rates are below 100 ?Sv/hr. Dose rates in the Visible-IR diagnostic model after one day of shutdown were 130 ?Sv/hr but fell below the limit to 90 ?Sv/hr 2-weeks later. The Large Aperture style shielding model exhibited higher and more persistent dose rates. After 1-day the dose rate was 230 ?Sv/hr but was still at 120 ?Sv/hr 4-weeks later.

  13. ITER Ion Cyclotron Heating and Fueling Systems

    SciTech Connect (OSTI)

    Rasmussen, D.A.; Baylor, L.R.; Combs, S.K.; Fredd, E.; Goulding, R.H.; Hosea, J.; Swain, D.W.

    2005-04-15

    The ITER burning plasma and advanced operating regimes require robust and reliable heating and current drive and fueling systems. The ITER design documents describe the requirements and reference designs for the ion cyclotron and pellet fueling systems. Development and testing programs are required to optimize, validate and qualify these systems for installation on ITER.The ITER ion cyclotron system offers significant technology challenges. The antenna must operate in a nuclear environment and withstand heat loads and disruption forces beyond present-day designs. It must operate for long pulse lengths and be highly reliable, delivering power to a plasma load with properties that will change throughout the discharge. The ITER ion cyclotron system consists of one eight-strap antenna, eight rf sources (20 MW, 35-65 MHz), associated high-voltage DC power supplies, transmission lines and matching and decoupling components.The ITER fueling system consists of a gas injection system and multiple pellet injectors for edge fueling and deep core fueling. Pellet injection will be the primary ITER fuel delivery system. The fueling requirements will require significant extensions in pellet injector pulse length ({approx}3000 s), throughput (400 torr-L/s,) and reliability. The proposed design is based on a centrifuge accelerator fed by a continuous screw extruder. Inner wall pellet injection with the use of curved guide tubes will be utilized for deep fueling.

  14. Alfven Eigenmode Stability with Beams in ITER-like Plasma

    SciTech Connect (OSTI)

    N.N. Gorelenkov; H.L. Berk; R.V. Budny

    2004-07-16

    Toroidicity Alfven Eigenmodes (TAE) in ITER can be driven unstable by two groups of energetic particles, the 3.5 MeV {alpha}-particle fusion products and the tangentially injected 1MeV beam ions. Stability conditions are established using the perturbative NOVA/NOVA-K codes. A quasi-linear diffusion model is then used to assess the induced redistribution of energetic particles.

  15. Nuclear modules of ITER tokamak systems code

    SciTech Connect (OSTI)

    Gohar, Y.; Baker, C.; Brooks, J.; Finn, P.; Hassanein, A.; Willms, S.; Barr, W.; Bushigin, A.; Kalyanam, K.M.; Haines, J.

    1987-10-01

    Nuclear modules were developed to model various reactor components in the ITER systems code. Several design options and cost algorithms are included for each component. The first wall, blanket and shield modules calculate the beryllium zone thickness, the disruptions results, the nuclear responses in different components including the toroidal field coils. Tungsten shield/water coolant/steel structure and steel shield/water coolant are the shield options for the inboard and outboard sections of the reactor. Lithium nitrate dissolved in the water coolant with a variable beryllium zone thickness in the outboard section of the reactor provides the tritium breeding capability. The reactor vault module defines the thickness of the reactor wall and the roof based on the dose equivalent during operation including skyshine contribution. The impurity control module provides the design parameters for the divertor including plate design, heat load, erosion rate, tritium permeation through the plate material to the coolant, plasma contamination by sputtered impurities, and plate lifetime. Several materials: Be, C, V, Mo, and W can be used for the divertor plate to cover a range of plasma edge temperatures. The tritium module calculates tritium and deuterium flow rates for the reactor plant. The tritium inventory in the fuelers, neutral beams, vacuum pumps, impurity control, first wall, and blanket is calculated. Tritium requirements are provided for different operating conditions. The nuclear models are summarized in this paper including the different design options and key analyses of each module. 39 refs., 3 tabs.

  16. Evaluating iterative reconstruction performance in computed tomography

    SciTech Connect (OSTI)

    Chen, Baiyu Solomon, Justin; Ramirez Giraldo, Juan Carlos; Samei, Ehsan

    2014-12-15

    Purpose: Iterative reconstruction (IR) offers notable advantages in computed tomography (CT). However, its performance characterization is complicated by its potentially nonlinear behavior, impacting performance in terms of specific tasks. This study aimed to evaluate the performance of IR with both task-specific and task-generic strategies. Methods: The performance of IR in CT was mathematically assessed with an observer model that predicted the detection accuracy in terms of the detectability index (d′). d′ was calculated based on the properties of the image noise and resolution, the observer, and the detection task. The characterizations of image noise and resolution were extended to accommodate the nonlinearity of IR. A library of tasks was mathematically modeled at a range of sizes (radius 1–4 mm), contrast levels (10–100 HU), and edge profiles (sharp and soft). Unique d′ values were calculated for each task with respect to five radiation exposure levels (volume CT dose index, CTDI{sub vol}: 3.4–64.8 mGy) and four reconstruction algorithms (filtered backprojection reconstruction, FBP; iterative reconstruction in imaging space, IRIS; and sinogram affirmed iterative reconstruction with strengths of 3 and 5, SAFIRE3 and SAFIRE5; all provided by Siemens Healthcare, Forchheim, Germany). The d′ values were translated into the areas under the receiver operating characteristic curve (AUC) to represent human observer performance. For each task and reconstruction algorithm, a threshold dose was derived as the minimum dose required to achieve a threshold AUC of 0.9. A task-specific dose reduction potential of IR was calculated as the difference between the threshold doses for IR and FBP. A task-generic comparison was further made between IR and FBP in terms of the percent of all tasks yielding an AUC higher than the threshold. Results: IR required less dose than FBP to achieve the threshold AUC. In general, SAFIRE5 showed the most significant dose reduction potentials (11–54 mGy, 77%–84%), followed by SAFIRE3 (7–36 mGy, 50%–61%) and IRIS (6–26 mGy, 37%–50%). The dose reduction potentials highly depended on task size and task contrast, with tasks of lower contrasts and smaller sizes, i.e., more challenging tasks, indicating higher dose reductions. Softer edge profile showed higher dose reduction potentials with SAFIRE3 and SAFIRE5, but not with IRIS. The task-generic comparison between IR and FBP demonstrated the overall superiority of IR performance, as IR allowed a larger percent of tasks to exceed the threshold AUC: IRIS, 8%–12%; SAFIRE3, 10%–16%; and SAFIRE5, 20%–33%. The improvement with IR was generally more pronounced at lower dose levels. Conclusions: Expanding beyond traditional contrast and noise based assessments of IR, we performed both task-specific and task-generic evaluations of IR performance. The task-specific evaluation demonstrated the dependency of IR’s dose reduction potential on task attributes, which can be employed to optimize IR for clinical indications with specific range of size and contrast. The task-generic evaluation demonstrated IR’s overall superiority over FBP in terms of the range of tasks exceeding a threshold performance level, which can be employed for general comparisons between algorithms.

  17. Anderson Acceleration for Fixed-Point Iterations

    SciTech Connect (OSTI)

    Walker, Homer F.

    2015-08-31

    The purpose of this grant was to support research on acceleration methods for fixed-point iterations, with applications to computational frameworks and simulation problems that are of interest to DOE.

  18. GENERAL CONDITIONS FOR ITER ORGANIZATION SERVICE CONTRACTS

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    1 GENERAL CONDITIONS FOR ITER ORGANIZATION SERVICE CONTRACTS (2014) Definitions ..................................................................................................................... 3 Article 1. Law and language of the Contract ................................................................................. 3 Article 2. Communications ............................................................................................................ 3 Article 3. Performance of the

  19. Novel aspects of plasma control in ITER

    SciTech Connect (OSTI)

    Humphreys, D.; Jackson, G.; Walker, M.; Welander, A.; Ambrosino, G.; Pironti, A.; Felici, F.; Kallenbach, A.; Raupp, G.; Treutterer, W.; Kolemen, E.; Lister, J.; Sauter, O.; Moreau, D.; Schuster, E.

    2015-02-15

    ITER plasma control design solutions and performance requirements are strongly driven by its nuclear mission, aggressive commissioning constraints, and limited number of operational discharges. In addition, high plasma energy content, heat fluxes, neutron fluxes, and very long pulse operation place novel demands on control performance in many areas ranging from plasma boundary and divertor regulation to plasma kinetics and stability control. Both commissioning and experimental operations schedules provide limited time for tuning of control algorithms relative to operating devices. Although many aspects of the control solutions required by ITER have been well-demonstrated in present devices and even designed satisfactorily for ITER application, many elements unique to ITER including various crucial integration issues are presently under development. We describe selected novel aspects of plasma control in ITER, identifying unique parts of the control problem and highlighting some key areas of research remaining. Novel control areas described include control physics understanding (e.g., current profile regulation, tearing mode (TM) suppression), control mathematics (e.g., algorithmic and simulation approaches to high confidence robust performance), and integration solutions (e.g., methods for management of highly subscribed control resources). We identify unique aspects of the ITER TM suppression scheme, which will pulse gyrotrons to drive current within a magnetic island, and turn the drive off following suppression in order to minimize use of auxiliary power and maximize fusion gain. The potential role of active current profile control and approaches to design in ITER are discussed. Issues and approaches to fault handling algorithms are described, along with novel aspects of actuator sharing in ITER.

  20. Project Manager, U.S. ITER INSIDE: ITER Site Progress Washington

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    ITER Organization has to change accordingly: It will become simpler, centralized, and task-force oriented to adapt to the new era of construction. Among our most important...

  1. An iterative learning controller for nonholonomic mobile robots

    SciTech Connect (OSTI)

    Oriolo, G.; Panzieri, S.; Ulivi, G.

    1998-09-01

    The authors present an iterative learning controller that applies to nonholonomic mobile robots, as well as other systems that can be put in chained form. The learning algorithm exploits the fact that chained-form. The learning algorithm exploits the fact that chained-form systems are linear under piecewise-constant inputs. The proposed control scheme requires the execution of a small number of experiments to drive the system to the desired state in finite time, with nice convergence and robustness properties with respect to modeling inaccuracies as well as disturbances. To avoid the necessity of exactly reinitializing the system at each iteration, the basic method is modified so as to obtain a cyclic controller, by which the system is cyclically steered through an arbitrary sequence of states. As a case study, a carlike mobile robot is considered. Both simulation and experimental results are reported to show the performance of the method.

  2. Microsoft Word - ex9rdf-ITER-sept09.doc

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    RDF - Technical Data - ITER UT-B Contracts Div Sept 2009 Page 1 of 5 ex9rdf-ITER-sept09.doc Exhibit 9RDF-ITER Ref: DEAR 970.5227-1 TECHNICAL DATA - ITER (Sept 2009) 1. Rights in ...

  3. Microsoft Word - ex9-ITER-june11.doc

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Data - ITER UT-B Contracts Div June 2011 Page 1 of 5 ex9-ITER-june11.doc Exhibit 9 ITER Ref: DEAR 927.409; FAR 52.227-14, 52.227-14 Alt.V, 52.227-16 TECHNICAL DATA - ITER (June ...

  4. Status of the ITER Tokamac Exhaust Process System

    Office of Environmental Management (EM)

    the ITER Tokamak Exhaust Process System Anita Poore Bernice Rogers 2014 Spring Tritium Focus Group Meeting April 24, 2014 SRNL-STI-2014-00175 The views and opinions expressed herein do not necessarily reflect those of the ITER Organization, US ITER or the US Government. Presentation Outline * Overview of ITER DT Fuel Cycle * Select ITER requirements Fuel Cycle * Process Requirements * Design Approach * Simplified Process Flow Diagram * Spatial Interface * Risk Mitigation Activities * Potential

  5. Global ICRF system designs for ITER and TPX

    SciTech Connect (OSTI)

    Goulding, R.H.; Hoffman, D.J.; Ryan, P.M.; Durodie, F.

    1995-09-01

    The design of feed networks for ICRF antenna arrays on ITER and TPX are discussed. Features which are present in one or both of the designs include distribution of power to several straps from a single generator, the capability to vary phases of the currents on antenna elements rapidly without the need to rematch, and passive elements which present a nearly constant load to the generators during ELM induced loading transients of a factor of I0 or more. The FDAC (Feedline/Decoupler/Antenna Calculator) network modeling code is described, which allows convenient modeling of the electrical performance of nearly arbitrary ICRF feed networks.

  6. Preliminary Master Logic Diagram for ITER operation

    SciTech Connect (OSTI)

    Cadwallader, L.C.; Taylor, N.P.; Poucet, A.E.

    1998-04-01

    This paper describes the work performed to develop a Master Logic Diagram (MLD) for the operations phase of the International Thermonuclear Experimental Reactor (ITER). The MLD is a probabilistic risk assessment tool used to identify the broad set of potential initiating events that could lead to an offsite radioactive or toxic chemical release from the facility under study. The MLD described here is complementary to the failure modes and effects analyses (FMEAs) that have been performed for ITER`s major plant systems in the engineering evaluation of the facility design. While the FMEAs are a bottom-up or component level approach, the MLD is a top-down or facility level approach to identifying the broad spectrum of potential events. Strengths of the MLD are that it analyzes the entire plant, depicts completeness in the accident initiator process, provides an independent method for identification, and can also identify potential system interactions. MLDs have been used successfully as a hazard analysis tool. This paper describes the process used for the ITER MLD to treat the variety of radiological and toxicological source terms present in the ITER design. One subtree of the nineteen page MLD is shown to illustrate the levels of the diagram.

  7. DOE/SC Lehman Review of US ITER Project, USIPO,

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    SC Lehman Review of US ITER Project, USIPO, Oak Ridge, Tennessee, April 5-7, 2011 - Ned Sauthoff Project Manager, US ITER INSIDE: ITER Site Progress Secret City View from DOE US Project Highlights Engaging Industry New PPPL Head of ITER Department PPPL to Cadarache New Division Director Positions Open at US ITER Upcoming Events ORNL 2011-G00858/jpp It has been a busy season for US ITER, as the team positions for fabrication in late-FY 12 and FY 13. Our priorities remain completing designs,

  8. Models and Datasets

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    iteration by iteration. RevSim is an Excel 2010 based model. Much of the logic is VBA code (Visual Basic for Applications); the user does not need to know VBA to run the...

  9. Non-iterative Voltage Stability

    SciTech Connect (OSTI)

    Makarov, Yuri V.; Vyakaranam, Bharat; Hou, Zhangshuan; Wu, Di; Meng, Da; Wang, Shaobu; Elbert, Stephen T.; Miller, Laurie E.; Huang, Zhenyu

    2014-09-30

    This report demonstrates promising capabilities and performance characteristics of the proposed method using several power systems models. The new method will help to develop a new generation of highly efficient tools suitable for real-time parallel implementation. The ultimate benefit obtained will be early detection of system instability and prevention of system blackouts in real time.

  10. Axisymmetric Simulations of the ITER Vertical Stability Coil

    SciTech Connect (OSTI)

    Titus, Peter H.

    2013-07-09

    The ITER in-vessel coil system includes Vertical Stability (VS) coils and Edge Localized Mode (ELM) coils. There are two large VS ring coils, one upper and one lower. Each has four turns which are independently connected. The VS coils are needed for successful operation of ITER for most all of its operating modes. The VS coils must be highly reliable and fault tolerant. The operating environment includes normal and disruption Lorentz forces. To parametrically address all these design conditions in a tractable analysis requires a simplified model. The VS coils are predominately axisymmetric, and this suggests that an axisymmetric model can be meaningfully used to address the variations in mechanical design, loading, material properties, and time dependency. The axisymmetric finite element analysis described in this paper includes simulations of the bolted frictional connections used for the mounting details. Radiation and elastic-plastic response are modeled particularly for the extreme faulted conditions. Thermal connectivity is varied to study the effects of partial thermal connection of the actively cooled conductor to the remaining structure.

  11. Annex I ITER Organization Service Contract General Conditions...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    All property of the Contractor while at the ITER Organization premises shall be at the risk of the Contractor and the ITER Organization shall accept no liability for any loss or...

  12. Annex I ITER Organization Service Contract General Conditions (2014)

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Annex I ITER Organization Service Contract General Conditions (2014) Page 1 of 21 GENERAL CONDITIONS FOR ITER ORGANIZATION SERVICE CONTRACTS (2014) Definitions ..................................................................................................................... 3 Article 1. Law and language of the Contract ................................................................................. 3 Article 2. Communications

  13. A domain decomposition method of stochastic PDEs: An iterative solution techniques using a two-level scalable preconditioner

    SciTech Connect (OSTI)

    Subber, Waad Sarkar, Abhijit

    2014-01-15

    Recent advances in high performance computing systems and sensing technologies motivate computational simulations with extremely high resolution models with capabilities to quantify uncertainties for credible numerical predictions. A two-level domain decomposition method is reported in this investigation to devise a linear solver for the large-scale system in the Galerkin spectral stochastic finite element method (SSFEM). In particular, a two-level scalable preconditioner is introduced in order to iteratively solve the large-scale linear system in the intrusive SSFEM using an iterative substructuring based domain decomposition solver. The implementation of the algorithm involves solving a local problem on each subdomain that constructs the local part of the preconditioner and a coarse problem that propagates information globally among the subdomains. The numerical and parallel scalabilities of the two-level preconditioner are contrasted with the previously developed one-level preconditioner for two-dimensional flow through porous media and elasticity problems with spatially varying non-Gaussian material properties. A distributed implementation of the parallel algorithm is carried out using MPI and PETSc parallel libraries. The scalabilities of the algorithm are investigated in a Linux cluster.

  14. International Workshop: MFE Roadmapping in the ITER Era | Princeton Plasma

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Physics Lab International Workshop: MFE Roadmapping in the ITER Era International Workshop: MFE Roadmapping in the ITER Era Contact Information Website: International Workshop: MFE Roadmapping in the ITER Era Coordinator(s): Pamela Hampton phampton@pppl.gov Host(s): G.H. Neilson hneilson@pppl.gov Learn More Fusion roadmapping

  15. Microsoft Word - ex9ed-ITER-june11.doc

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    ED - Technical Data - ITER UT-B Contracts Div June 2011 Page 1 of 5 ex9ed-ITER-june11.doc ... IV, 52.227-14 Alt. V, 52.227-16 TECHNICAL DATA - ITER (June 2011) 1. RIGHTS IN ...

  16. Annex II Technical Specifications Project Integration of ITER

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Project Integration of ITER Neutron Diagnostics ITER_D_SSYW98 v 2.0 ITER_D_R83AFD Page 2 of 8 Table of Contents 1 Abstract .................................................................................. Error! Bookmark not defined. 2 Background and Objectives ...............................................................................................3 3 Scope of Work ......................................................................................................................4 4

  17. A Comparison of Modifications to MELCOR versions 1.8.2 and 1.8.6 for ITER Safety Analysis

    SciTech Connect (OSTI)

    B. J. Merrill; P. W. Humrickhouse

    2010-06-01

    During the Engineering Design Activity of the International Thermonuclear Experimental Reactor (ITER), the MELCOR 1.8.2 code was selected as one of several codes to be used to perform ITER safety analyses [1]. MELCOR was chosen because it has the capability of predicting coolant pressure, temperature, mass flow rate, and radionuclide and aerosol transport in nuclear facilities and reactor cooling systems. MELCOR can also predict structural temperatures (e.g. first wall, blanket, divertor, and vacuum vessel) resulting from energy produced by radioactive decay heat and/or chemical reactions (oxidation). The Idaho National Laboratory (INL) Fusion Safety Program (FSP) made fusion specific modifications to the MELCOR 1.8.2 code [2-6], including models for water freezing, air condensation, beryllium, carbon, and tungsten oxidation in steam and air environments, flow boiling in coolant loops, and radiation in enclosures, that allowed MELCOR to assess the thermal hydraulic response of ITER cooling systems and the transport of radionuclides as aerosols during accident conditions. Recently, the ITER International Organization (IO) used a “pedigreed” version of MELCOR 1.8.2 [7] to perform accident analyses for ITER’s “Rapport Préliminaire de Sûreté” (Report Preliminary on Safety - RPrS). The MELCOR thermal-hydraulics code [8] is currently under development at the Sandia National Laboratory (SNL) for the US Nuclear Regulatory Commission (NRC). MELCOR is used to model the progression of severe accidents in light water fission reactors. Because MELCOR has undergone many improvements between version 1.8.2 and 1.8.6, the INL FSP decided to introduce fusion modifications into MELCOR 1.8.6, and thereby produce a version of MELCOR 1.8.6 with similar capabilities to the pedigreed version of MELCOR 1.8.2 used for the ITER RPrS. We have applied this version of MELCOR 1.8.6 to the same set of problems used in the MELCOR 1.8.2 pedigree analysis [7]. Section 2 describes a non-regression analysis that involves comparing the results from the modified version of MELCOR 1.8.6 against those predicted by the original, unmodified version of MELCOR 1.8.6. The purpose of this non-regression analysis is to demonstrate that the modifications made to the MELCOR 1.8.6 code do not drastically alter the intended functions of the MELCOR base code, and if they do to explain why the departure occurs and if the change is needed. The analysis was performed using the demonstration problem that came with the MELCOR 1.8.6 source distribution. Section 3 makes a comparison between the pedigreed version of MELCOR 1.8.2 and the new modified version of MELCOR 1.8.6 on a set of accident problems used by the ITER Joint Central Team (JCT) in the Generic Site Safety Report (GSSR) [9]. Finally, in section 4, the two versions of the code are compared on a series of developmental test problems described in the change documents [2-4, 6].

  18. The workshop on iterative methods for large scale nonlinear problems

    SciTech Connect (OSTI)

    Walker, H.F.; Pernice, M.

    1995-12-01

    The aim of the workshop was to bring together researchers working on large scale applications with numerical specialists of various kinds. Applications that were addressed included reactive flows (combustion and other chemically reacting flows, tokamak modeling), porous media flows, cardiac modeling, chemical vapor deposition, image restoration, macromolecular modeling, and population dynamics. Numerical areas included Newton iterative (truncated Newton) methods, Krylov subspace methods, domain decomposition and other preconditioning methods, large scale optimization and optimal control, and parallel implementations and software. This report offers a brief summary of workshop activities and information about the participants. Interested readers are encouraged to look into an online proceedings available at http://www.usi.utah.edu/logan.proceedings. In this, the material offered here is augmented with hypertext abstracts that include links to locations such as speakers` home pages, PostScript copies of talks and papers, cross-references to related talks, and other information about topics addresses at the workshop.

  19. Statistical properties of an iterated arithmetic mapping

    SciTech Connect (OSTI)

    Feix, M.R.; Rouet, J.L.

    1994-07-01

    We study the (3x = 1)/2 problem from a probabilistic viewpoint and show a forgetting mechanism for the last k binary digits of the seed after k iterations. The problem is subsequently generalized to a trifurcation process, the (lx + m)/3 problem. Finally the sequence of a set of seeds is empirically shown to be equivalent to a random walk of the variable log{sub 2}x (or log{sub 3} x) though computer simulations.

  20. US ITER is a strong contributor in plan to enhance international sharing of

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    prime ITER real estate | Princeton Plasma Physics Lab US ITER is a strong contributor in plan to enhance international sharing of prime ITER real estate American Fusion News Category: U.S. ITER Link: US ITER is a strong contributor in plan to enhance international sharing of prime ITER real estate

  1. In-vessel ITER tubing failure rates for selected materials and coolants

    SciTech Connect (OSTI)

    Marshall, T.D.; Cadwallader, L.C.

    1994-03-01

    Several materials have been suggested for fabrication of ITER in-vessel coolant tubing: beryllium, copper, Inconel, niobium, stainless steel, titanium, and vanadium. This report generates failure rates for the materials to identify the best performer from an operational safety and availability perspective. Coolant types considered in this report are helium gas, liquid lithium, liquid sodium, and water. Failure rates for the materials are generated by including the influence of ITER`s operating environment and anticipated tubing failure mechanisms with industrial operating experience failure rates. The analyses define tubing failure mechanisms for ITER as: intergranular attack, flow erosion, helium induced swelling, hydrogen damage, neutron irradiation embrittlement, cyclic fatigue, and thermal cycling. K-factors, multipliers, are developed to model each failure mechanism and are applied to industrial operating experience failure rates to generate tubing failure rates for ITER. The generated failure rates identify the best performer by its expected reliability. With an average leakage failure rate of 3.1e-10(m-hr){sup {minus}1}and an average rupture failure rate of 3.1e-11(m-hr){sup {minus}1}, titanium proved to be the best performer of the tubing materials. The failure rates generated in this report are intended to serve as comparison references for design safety and optimization studies. Actual material testing and analyses are required to validate the failure rates.

  2. Tungsten dust impact on ITER-like plasma edge

    SciTech Connect (OSTI)

    Smirnov, R. D. Krasheninnikov, S. I.; Pigarov, A. Yu.; Rognlien, T. D.

    2015-01-15

    The impact of tungsten dust originating from divertor plates on the performance of edge plasma in ITER-like discharge is evaluated using computer modeling with the coupled dust-plasma transport code DUSTT-UEDGE. Different dust injection parameters, including dust size and mass injection rates, are surveyed. It is found that tungsten dust injection with rates as low as a few mg/s can lead to dangerously high tungsten impurity concentrations in the plasma core. Dust injections with rates of a few tens of mg/s are shown to have a significant effect on edge plasma parameters and dynamics in ITER scale tokamaks. The large impact of certain phenomena, such as dust shielding by an ablation cloud and the thermal force on tungsten ions, on dust/impurity transport in edge plasma and consequently on core tungsten contamination level is demonstrated. It is also found that high-Z impurities provided by dust can induce macroscopic self-sustained plasma oscillations in plasma edge leading to large temporal variations of edge plasma parameters and heat load to divertor target plates.

  3. Occupational Radiation Exposure Analysis of US ITER DCLL TBM

    SciTech Connect (OSTI)

    Merrill, Brad J; Cadwallader, Lee C; Dagher, Mohamad

    2007-08-01

    This report documents an Occupational Radiation Exposure (ORE) analysis that was performed for the US International Thermonuclear Experimental Reactor (ITER) Dual Coolant Lead Lithium (DCLL) Test Blanket Module (TBM). This analysis was performed with the QADMOD dose code for anticipated maintenance activities for this TBM concept and its ancillary systems. The QADMOD code was used to model the PbLi cooling loop of this TBM concept by specifying gamma ray source terms that simulated radioactive material within the piping, valves, heat exchanger, permeator, pump, drain tank, and cold trap of this cooling system. Estimates of the maintenance tasks that will have to be performed and the time required to perform these tasks where developed based on either expert opinion or on industrial maintenance experience for similar technologies. This report details the modeling activity and the calculated doses for the maintenance activities envisioned for the US DCLL TBM.

  4. PPPL's Hawryluk Named ITER Deputy Director-General | Princeton Plasma

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Physics Lab PPPL's Hawryluk Named ITER Deputy Director-General By Patti Wieser March 8, 2011 Tweet Widget Google Plus One Share on Facebook Richard Hawryluk (Photo by Elle Starkman, PPPL Office of Communications) Richard Hawryluk Richard Hawryluk, a senior scientist at the DOE Princeton Plasma Physics Laboratory (PPPL), has been appointed deputy director-general of the ITER Organization and director of its administration department. The ITER project, currently under construction in France,

  5. PPPL's Hawryluk Named ITER Deputy Director-General | Princeton Plasma

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Physics Lab PPPL's Hawryluk Named ITER Deputy Director-General By Patti Wieser March 8, 2011 Tweet Widget Google Plus One Share on Facebook Richard Hawryluk (Photo by Elle Starkman, PPPL Office of Communications) Richard Hawryluk Richard Hawryluk, a senior scientist at the DOE Princeton Plasma Physics Laboratory (PPPL), has been appointed deputy director-general of the ITER Organization and director of its administration department. The ITER project, currently under construction in France,

  6. Simulation and Analysis of the Hybrid Operating Mode in ITER

    SciTech Connect (OSTI)

    Kessel, C.E.; Budny, R.V.; Indireshkumar, K.

    2005-09-22

    The hybrid operating mode in ITER is examined with 0D systems analysis, 1.5D discharge scenario simulations using TSC and TRANSP, and the ideal MHD stability is discussed. The hybrid mode has the potential to provide very long pulses and significant neutron fluence if the physics regime can be produced in ITER. This paper reports progress in establishing the physics basis and engineering limitation for the hybrid mode in ITER.

  7. Diverse Power Iteration Embeddings and Its Applications

    SciTech Connect (OSTI)

    Huang H.; Yoo S.; Yu, D.; Qin, H.

    2014-12-14

    Abstract—Spectral Embedding is one of the most effective dimension reduction algorithms in data mining. However, its computation complexity has to be mitigated in order to apply it for real-world large scale data analysis. Many researches have been focusing on developing approximate spectral embeddings which are more efficient, but meanwhile far less effective. This paper proposes Diverse Power Iteration Embeddings (DPIE), which not only retains the similar efficiency of power iteration methods but also produces a series of diverse and more effective embedding vectors. We test this novel method by applying it to various data mining applications (e.g. clustering, anomaly detection and feature selection) and evaluating their performance improvements. The experimental results show our proposed DPIE is more effective than popular spectral approximation methods, and obtains the similar quality of classic spectral embedding derived from eigen-decompositions. Moreover it is extremely fast on big data applications. For example in terms of clustering result, DPIE achieves as good as 95% of classic spectral clustering on the complex datasets but 4000+ times faster in limited memory environment.

  8. Technological Institute of Renewable Energy ITER | Open Energy...

    Open Energy Info (EERE)

    to: navigation, search Name: Technological Institute of Renewable Energy (ITER) Place: Santa Cruz de Tenerife, Spain Zip: 38611 Sector: Solar, Wind energy Product: Spain-based,...

  9. PPPL's Rich Hawryluk recognized for service to ITER international...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Department. ITER is an international fusion experiment that is under construction in France. Hawryluk, a former deputy director of PPPL, completed a two-year assignment at...

  10. Microsoft Word - ex15-ITER-sept10.doc

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    5 - Rights in Data-Special Works - ITER UT-B Contracts Div Sept 2010 Page 1 of 1 ex15-ITER-sept10.doc Exhibit 15-ITER Ref: FAR 52.227-17 RIGHTS IN DATA í SPECIAL WORKS í ITER (Sept 2010) (a) Definitions. (1) "Data", as used in this clause, means recorded information, regardless of form or the media on which it may be recorded. The term includes technical data and computer software. The term does not include information incidental to contract administration, such as financial,

  11. Microsoft Word - ex1b-ITER-mar07.doc

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    B - Patent Rights - Acquisition by the Government - ITER UT-B Contracts Div March 2007 Page 1 of 6 ex1b-ITER-mar07.doc Exhibit 1B ITER Ref: DEAR 952.227-13 PATENT RIGHTS - ACQUISITION BY THE GOVERNMENT - ITER (Mar 2007) (a) Definitions. (1) "Invention", as used in this clause, means any invention or discovery which is or may be patentable or otherwise protectable under title 35 of the United States Code or any novel variety of plant that is or may be protectable under the Plant Variety

  12. Microsoft Word - ex9-ITER-june11.doc

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    - Technical Data - ITER UT-B Contracts Div June 2011 Page 1 of 5 ex9-ITER-june11.doc Exhibit 9 ITER Ref: DEAR 927.409; FAR 52.227-14, 52.227-14 Alt.V, 52.227-16 TECHNICAL DATA - ITER (June 2011) 1. RIGHTS IN DATA - GENERAL (a) Definitions. (1) "Computer data bases," as used in this clause, means a collection of data in a form capable of, and for the purpose of, being stored in, processed, and operated on by a computer. The term does not include computer software. (2) "Computer

  13. Microsoft Word - ex9ed-ITER-june11.doc

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    ED - Technical Data - ITER UT-B Contracts Div June 2011 Page 1 of 5 ex9ed-ITER-june11.doc Exhibit 9ED ITER Ref: DEAR 927.409; FAR 52.227-14, 52.227-14 Alt. IV, 52.227-14 Alt. V, 52.227-16 TECHNICAL DATA - ITER (June 2011) 1. RIGHTS IN DATA-GENERAL (a) Definitions. (1) "Computer data bases," as used in this clause, means a collection of data in a form capable of, and for the purpose of, being stored in, processed, and operated on by a computer. The term does not include computer

  14. Microsoft Word - ex9rdf-ITER-sept09.doc

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    RDF - Technical Data - ITER UT-B Contracts Div Sept 2009 Page 1 of 5 ex9rdf-ITER-sept09.doc Exhibit 9RDF-ITER Ref: DEAR 970.5227-1 TECHNICAL DATA - ITER (Sept 2009) 1. Rights in Data-Facilities. (a) Definitions. (1) "Computer Data Bases", as used in this clause, means a collection of data in a form capable of, and for the purpose of, being stored in, processed, and operated on by a computer. The term does not include Computer Software. (2) "Computer Software", as used in this

  15. An Iterated, Multipoint Differential Transform Method for Numerically...

    Office of Scientific and Technical Information (OSTI)

    ...Value Problems Citation Details In-Document Search Title: An Iterated, Multipoint Differential Transform Method for Numerically Evolving Partial Differential Equation Initial-Value ...

  16. COLLOQUIUM: ITER and its Diagnostics - Rising to the Challenge...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    measure the performance and provide the control signals for this device. A diagnostic set will be installed on the ITER machine to provide the measurements necessary to control, ...

  17. Physics and technology in the ion-cyclotron range of frequency on Tore Supra and TITAN test facility: implication for ITER

    SciTech Connect (OSTI)

    Litaudon, X; Bernard, J. M.; Colas, L.; Dumont, R. J.; Argouarch, A.; Bottollier-Curtet, H.; Bremond, S.; Champeaux, S.; Corre, Y.; Dumortier, P.; Firdaouss, M.; Guilhem, D.; Gunn, J. P.; Gouard, Ph.; Hoang, G T; Jacquot, Jonathan; Klepper, C Christopher; Kubic, M.; Kyrytsya, V.; Lombard, G.; Milanesio, D.; Messiaen, A.; Mollard, P.; Meyer, O.; Zarzoso, D.

    2013-01-01

    To support the design of an ITER ion-cyclotron range of frequency heating (ICRH) system and to mitigate risks of operation in ITER, CEA has initiated an ambitious Research & Development program accompanied by experiments on Tore Supra or test-bed facility together with a significant modelling effort. The paper summarizes the recent results in the following areas: Comprehensive characterization (experiments and modelling) of a new Faraday screen concept tested on the Tore Supra antenna. A new model is developed for calculating the ICRH sheath rectification at the antenna vicinity. The model is applied to calculate the local heat flux on Tore Supra and ITER ICRH antennas. Full-wave modelling of ITER ICRH heating and current drive scenarios with the EVE code. With 20 MW of power, a current of 400 kA could be driven on axis in the DT scenario. Comparison between DT and DT(3He) scenario is given for heating and current drive efficiencies. First operation of CW test-bed facility, TITAN, designed for ITER ICRH components testing and could host up to a quarter of an ITER antenna. R&D of high permittivity materials to improve load of test facilities to better simulate ITER plasma antenna loading conditions.

  18. Registration of range data using a hybrid simulated annealing and iterative closest point algorithm

    SciTech Connect (OSTI)

    LUCK,JASON; LITTLE,CHARLES Q.; HOFF,WILLIAM

    2000-04-17

    The need to register data is abundant in applications such as: world modeling, part inspection and manufacturing, object recognition, pose estimation, robotic navigation, and reverse engineering. Registration occurs by aligning the regions that are common to multiple images. The largest difficulty in performing this registration is dealing with outliers and local minima while remaining efficient. A commonly used technique, iterative closest point, is efficient but is unable to deal with outliers or avoid local minima. Another commonly used optimization algorithm, simulated annealing, is effective at dealing with local minima but is very slow. Therefore, the algorithm developed in this paper is a hybrid algorithm that combines the speed of iterative closest point with the robustness of simulated annealing. Additionally, a robust error function is incorporated to deal with outliers. This algorithm is incorporated into a complete modeling system that inputs two sets of range data, registers the sets, and outputs a composite model.

  19. ITER Generic Diagnostic Upper Port Plug Nuclear Heating and Personnel Dose Rate Assesment Neutronics Analysis using the ATTILA Discrete Ordinates Code

    SciTech Connect (OSTI)

    Russell Feder and Mahmoud Z. Yousef

    2009-05-29

    Neutronics analysis to find nuclear heating rates and personnel dose rates were conducted in support of the integration of diagnostics in to the ITER Upper Port Plugs. Simplified shielding models of the Visible-Infrared diagnostic and of the ECH heating system were incorporated in to the ITER global CAD model. Results for these systems are representative of typical designs with maximum shielding and a small aperture (Vis-IR) and minimal shielding with a large aperture (ECH). The neutronics discrete-ordinates code ATTILA and SEVERIAN (the ATTILA parallel processing version) was used. Material properties and the 500 MW D-T volume source were taken from the ITER Brand Model MCNP benchmark model. A biased quadrature set equivelant to Sn=32 and a scattering degree of Pn=3 were used along with a 46-neutron and 21-gamma FENDL energy subgrouping. Total nuclear heating (neutron plug gamma heating) in the upper port plugs ranged between 380 and 350 kW for the Vis-IR and ECH cases. The ECH or Large Aperture model exhibited lower total heating but much higher peak volumetric heating on the upper port plug structure. Personnel dose rates are calculated in a three step process involving a neutron-only transport calculation, the generation of activation volume sources at pre-defined time steps and finally gamma transport analyses are run for selected time steps. ANSI-ANS 6.1.1 1977 Flux-to-Dose conversion factors were used. Dose rates were evaluated for 1 full year of 500 MW DT operation which is comprised of 3000 1800-second pulses. After one year the machine is shut down for maintenance and personnel are permitted to access the diagnostic interspace after 2-weeks if dose rates are below 100 ?Sv/hr. Dose rates in the Visible-IR diagnostic model after one day of shutdown were 130 ?Sv/hr but fell below the limit to 90 ?Sv/hr 2-weeks later. The Large Aperture or ECH style shielding model exhibited higher and more persistent dose rates. After 1-day the dose rate was 230 ?Sv/hr but was still at 120 ?Sv/hr 4-weeks later. __________________________________________________

  20. A sequential partly iterative approach for multicomponent reactive transport with CORE2D

    SciTech Connect (OSTI)

    Samper, J.; Xu, T.; Yang, C.

    2008-11-01

    CORE{sup 2D} V4 is a finite element code for modeling partly or fully saturated water flow, heat transport and multicomponent reactive solute transport under both local chemical equilibrium and kinetic conditions. It can handle coupled microbial processes and geochemical reactions such as acid-base, aqueous complexation, redox, mineral dissolution/precipitation, gas dissolution/exsolution, ion exchange, sorption via linear and nonlinear isotherms, sorption via surface complexation. Hydraulic parameters may change due to mineral precipitation/dissolution reactions. Coupled transport and chemical equations are solved by using sequential iterative approaches. A sequential partly-iterative approach (SPIA) is presented which improves the accuracy of the traditional sequential noniterative approach (SNIA) and is more efficient than the general sequential iterative approach (SIA). While SNIA leads to a substantial saving of computing time, it introduces numerical errors which are especially large for cation exchange reactions. SPIA improves the efficiency of SIA because the iteration between transport and chemical equations is only performed in nodes with a large mass transfer between solid and liquid phases. The efficiency and accuracy of SPIA are compared to those of SIA and SNIA using synthetic examples and a case study of reactive transport through the Llobregat Delta aquitard in Spain. SPIA is found to be as accurate as SIA while requiring significantly less CPU time. In addition, SPIA is much more accurate than SNIA with only a minor increase in computing time. A further enhancement of the efficiency of SPIA is achieved by improving the efficiency of the Newton-Raphson method used for solving chemical equations. Such an improvement is obtained by working with increments of log-concentrations and ignoring the terms of the Jacobian matrix containing derivatives of activity coefficients. A proof is given for the symmetry and non-singularity of the Jacobian matrix. Numerical analyses performed with synthetic examples confirm that these modifications improve the efficiency and convergence of the iterative algorithm.

  1. Microsoft Word - Second_ ITER Council Press Release.doc

    Energy Savers [EERE]

    Neil Calder Tel: 00 33 (0)6 14 16 41 75 ITER GAINS MOMENTUM Aomori, Japan 18 June 2008 On 17-18 June 2008, the ITER Council, the Governing Body of the new international Organization, convened for its second meeting. The two day meeting in Aomori, Japan, brought together senior representatives from the seven ITER Members: China, the European Union, India, Japan, Korea, Russia and the United States. Mr. Shingo Mimura, Governor of the Aomori Prefecture, welcomed delegates with a reminder of the

  2. Princeton Plasma Physics Lab - U.S. ITER

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Video Looks at ITER http:www.pppl.govnode1536

  3. An Overview Of The ITER In-Vessel Coil Systems

    SciTech Connect (OSTI)

    Heitzenroeder, P J; Chrzanowski, J H; Dahlgren, F; Hawryluk, R J; Loesser, G D; Neumeyer, C; Mansfield, C; Smith, J P; Schaffer, M; Humphreys, D; Cordier, J J; Campbell, D; Johnson, G A; Martin, A; Rebut, P H; Tao, J O; Fogarty, P J; Nelson, B E

    2009-09-24

    ELM mitigation is of particular importance in ITER in order to prevent rapid erosion or melting of the divertor surface, with the consequent risk of water leaks, increased plasma impurity content and disruptivity. Exploitable "natural" small or no ELM regimes might yet be found which extrapolate to ITER but this cannot be depended upon. Resonant Magnetic Perturbation has been added to pellet pacing as a tool for ITER to mitigate ELMs. Both are required, since neither method is fully developed and much work remains to be done. In addition, in-vessel coils enable vertical stabilization and RWM control. For these reasons, in-vessel coils (IVCs) are being designed for ITER to provide control of Edge Localized Modes (ELMs) in addition to providing control of moderately unstable resistive wall modes (RWMs) and the vertical stability (VS) of the plasma.

  4. Electrostatic Dust Detection and Removal for ITER

    SciTech Connect (OSTI)

    C.H. Skinner; A. Campos; H. Kugel; J. Leisure; A.L. Roquemore; S. Wagner

    2008-09-01

    We present some recent results on two innovative applications of microelectronics technology to dust inventory measurement and dust removal in ITER. A novel device to detect the settling of dust particles on a remote surface has been developed in the laboratory. A circuit board with a grid of two interlocking conductive traces with 25 μm spacing is biased to 30 – 50 V. Carbon particles landing on the energized grid create a transient short circuit. The current flowing through the short circuit creates a voltage pulse that is recorded by standard nuclear counting electronics and the total number of counts is related to the mass of dust impinging on the grid. The particles typically vaporize in a few seconds restoring the previous voltage standoff. Experience on NSTX however, showed that in a tokamak environment it was still possible for large particles or fibers to remain on the grid causing a long term short circuit. We report on the development of a gas puff system that uses helium to clear such particles. Experiments with varying nozzle designs, backing pressures, puff durations, and exit flow orientations have given an optimal configuration that effectively removes particles from an area up to 25 cm² with a single nozzle. In a separate experiment we are developing an advanced circuit grid of three interlocking traces that can generate a miniature electrostatic traveling wave for transporting dust to a suitable exit port. We have fabricated such a 3-pole circuit board with 25 micron insulated traces that operates with voltages up to 200 V. Recent results showed motion of dust particles with the application of only 50 V bias voltage. Such a device could potentially remove dust continuously without dedicated interventions and without loss of machine availability for plasma operations.

  5. PPPL's Rich Hawryluk recognized for service to ITER international fusion

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    project | Princeton Plasma Physics Lab PPPL's Rich Hawryluk recognized for service to ITER international fusion project By John Greenwald July 23, 2013 Tweet Widget Google Plus One Share on Facebook (Photo by U.S. Department of Energy) Gallery: From left, Energy Secretary Ernest Moniz and Rich Hawryluk (Photo by U.S. Department of Energy) From left, Energy Secretary Ernest Moniz and Rich Hawryluk Rich Hawryluk served as Deputy Director-General for the ITER Organization and Director of the

  6. United States and International Partners Initial ITER Agreement |

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Department of Energy International Partners Initial ITER Agreement United States and International Partners Initial ITER Agreement May 24, 2006 - 10:48am Addthis Paves the Way for Large-Scale, Clean Fusion Energy Project BRUSSELS, BELGIUM - Representing the United States, Dr. Raymond L. Orbach, Director of the U.S. Department of Energy's (DOE) Office of Science, joined counterparts from China, the European Union, India, Japan, the Republic of Korea, and the Russian Federation today to

  7. An Iterated, Multipoint Differential Transform Method for Numerically

    Office of Scientific and Technical Information (OSTI)

    Evolving Partial Differential Equation Initial-Value Problems (Journal Article) | SciTech Connect Journal Article: An Iterated, Multipoint Differential Transform Method for Numerically Evolving Partial Differential Equation Initial-Value Problems Citation Details In-Document Search Title: An Iterated, Multipoint Differential Transform Method for Numerically Evolving Partial Differential Equation Initial-Value Problems Authors: Finkel, H. J. [1] + Show Author Affiliations (LCF) Publication

  8. French landmark decree authorizes ITER construction | Princeton Plasma

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Physics Lab French landmark decree authorizes ITER construction By John Greenwald November 20, 2012 Tweet Widget Google Plus One Share on Facebook The French government has capped more than two years of review by issuing a license for the construction of ITER, the international fusion project that the European Union, the United States and five other countries are building in Cadarache, France, to demonstrate the feasibility of fusion energy. French Prime Minister Jean-Marc Ayrault signed the

  9. A review of the US joining technologies for plasma facing components in the ITER fusion reactor

    SciTech Connect (OSTI)

    Odegard, B.C. Jr.; Cadden, C.H.; Watson, R.D.; Slattery, K.T.

    1998-02-01

    This paper is a review of the current joining technologies for plasma facing components in the US for the International Thermonuclear Experimental Reactor (ITER) project. Many facilities are involved in this project. Many unique and innovative joining techniques are being considered in the quest to join two candidate armor plate materials (beryllium and tungsten) to a copper base alloy heat sink (CuNiBe, OD copper, CuCrZr). These techniques include brazing and diffusion bonding, compliant layers at the bond interface, and the use of diffusion barrier coatings and diffusion enhancing coatings at the bond interfaces. The development and status of these joining techniques will be detailed in this report.

  10. A comparison of conjugate gradient, SIP, and other iterative methods for the solution of Poisson's equation with irregular boundary conditions

    SciTech Connect (OSTI)

    Bergmann, D.J.

    1990-06-01

    Several well known iterative methods for solving Poisson's equation, including Strongly Implicit Procedure and several preconditioned conjugate gradient methods are first applied to a problem with simple boundary conditions and a known solution. Then a problem with more complicated boundary conditions, similar to those encountered when modeling AVLIS plasmas, is solved. Differences in the solutions of the various methods are examined through the use of Fourier analysis. It was found that combinations of different iterative schemes will in some cases be the most efficient method of solution. 22 refs., 29 figs.

  11. Examination of the Entry to Burn and Burn Control for the ITER 15 MA Baseline and Other Scenarios

    SciTech Connect (OSTI)

    Kesse, Charles E.; Kim, S-H.; Koechl, F.

    2014-09-01

    The entry to burn and flattop burn control in ITER will be a critical need from the first DT experiments. Simulations are used to address time-dependent behavior under a range of possible conditions that include injected power level, impurity content (W, Ar, Be), density evolution, H-mode regimes, controlled parameter (Wth, Pnet, Pfusion), and actuator (Paux, fueling, fAr), with a range of transport models. A number of physics issues at the L-H transition require better understanding to project to ITER, however, simulations indicate viable control with sufficient auxiliary power (up to 73 MW), while lower powers become marginal (as low as 43 MW).

  12. Science and Technology Research and Development in Support to ITER and the Broader Approach at CEA

    SciTech Connect (OSTI)

    Becoulet, A.; Hoang, G T; Abiteboul, J.; Achard, J.; Alarcon, T.; Klepper, C Christopher

    2013-01-01

    In parallel to the direct contribution to the procurement phase of ITER and Broader Approach, CEA has initiated research & development programmes, accompanied by experiments together with a significant modelling effort, aimed at ensuring robust operation, plasma performance, as well as mitigating the risks of the procurement phase. This overview reports the latest progress in both fusion science and technology including many areas, namely the mitigation of superconducting magnet quenches, disruption-generated runaway electrons, edge-localized modes (ELMs), the development of imaging surveillance, and heating and current drive systems for steady-state operation. The WEST (W Environment for Steady-state Tokamaks) project, turning Tore Supra into an actively cooled W-divertor platform open to the ITER partners and industries, is presented.

  13. Evaluation of graphite/steam interactions for ITER (International Thermonuclear Experimental Reactor)

    SciTech Connect (OSTI)

    Smolik, G.R.; Merrill, B.J.; Piet, S.J.; Holland, D.F.

    1990-09-01

    In this report we present the results of an experimental/analytical study designed to determine the quantity of hydrogen generated during a coolant inleakage accident in ITER. This hydrogen could represent a potential explosive hazard, provided the proper conditions exist, causing machine damage and release of radioactive material. We have measured graphite/steam reaction rates for several graphites and carbon-based composites at temperatures between 1000 C and 1700 C. The effects of steam flow rate, and partial pressure were also examined. The measured reaction rates correlated well with two Arrhenius type relationships. We have used the relationships for GraphNOL N3M in a thermal model to determine that for ITER the quantity of hydrogen produced would range between 5 and 35 kg, depending upon how the graphite tiles are attached to the first wall. While 5 kg is not a significant concern, 35 kg presents an explosive hazard. 20 refs., 14 figs., 1 tab.

  14. Benchmark of numerical tools simulating beam propagation and secondary particles in ITER NBI

    SciTech Connect (OSTI)

    Sartori, E. Veltri, P.; Serianni, G.; Dlougach, E.; Hemsworth, R.; Singh, M.

    2015-04-08

    Injection of high energy beams of neutral particles is a method for plasma heating in fusion devices. The ITER injector, and its prototype MITICA (Megavolt ITER Injector and Concept Advancement), are large extrapolations from existing devices: therefore numerical modeling is needed to set thermo-mechanical requirements for all beam-facing components. As the power and charge deposition originates from several sources (primary beam, co-accelerated electrons, and secondary production by beam-gas, beam-surface, and electron-surface interaction), the beam propagation along the beam line is simulated by comprehensive 3D models. This paper presents a comparative study between two codes: BTR has been used for several years in the design of the ITER HNB/DNB components; SAMANTHA code was independently developed and includes additional phenomena, such as secondary particles generated by collision of beam particles with the background gas. The code comparison is valuable in the perspective of the upcoming experimental operations, in order to prepare a reliable numerical support to the interpretation of experimental measurements in the beam test facilities. The power density map calculated on the Electrostatic Residual Ion Dump (ERID) is the chosen benchmark, as it depends on the electric and magnetic fields as well as on the evolution of the beam species via interaction with the gas. Finally the paper shows additional results provided by SAMANTHA, like the secondary electrons produced by volume processes accelerated by the ERID fringe-field towards the Cryopumps.

  15. Commitment to Public Involvement

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Create a Sustainable Future Commitment to Public Involvement Commitment to Public Involvement LANL is committed to our neighbors August 1, 2013 Lab Director McMillan talks with...

  16. DESIGN, ANALYSIS AND TEST CONCEPT FOR PROTOTYPE CRYOLINE OF ITER

    SciTech Connect (OSTI)

    Sarkar, B.; Badgujar, S.; Vaghela, H.; Shah, N.; Bhattacharya, R.; Chakrapani, Ch.

    2008-03-16

    The ITER cryo-distribution and cryoline is a part of the in-kind supply for India. The design of the systems is in progress. The topology of torus and neutral beam cryoline is defined as six process pipes along with thermal shield at 80 K and outer vacuum jacket. In order to develop confidence in the concept and to establish the high level of engineering and manufacturing technology, a prototype testing has been proposed. The prototype test will be carried out on 1:1 model in terms of dimension. However, the mass flow rate of the supercritical helium at 4.5 K and gaseous helium at 80 K will be on a 1:10 scale. The prototype cryoline has been designed and analyzed for thermal, structural and hydraulic parameters. The objective of this prototype test is to verify mechanical behavior due to thermal stress and pressure force, thermal and hydraulic performances. The concept of test facility has been realized along with the Piping and Instrumentation (P and I) diagram, instrumentation, controls, data acquisition, 80 K helium generation system along with supply and return valve boxes and interfacing hardware. The design concept, methodology for analysis and results, as well as the test facility have been discussed.

  17. Modeling

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Reacting Flow/Modeling Modelingadmin2015-10-28T02:39:13+00:00 Turbulence models typically involve coarse-graining and/or time averaging. Though adequate for modeling mean transport, this approach does not address turbulence-microphysics interactions that are important in combustion processes. Subgrid models are developed to represent these interactions. The CRF has developed a fundamentally different representation of these interactions that does not involve distinct coarse-grained and subgrid

  18. Electromagnetic analysis of forces and torques on the baseline and enhanced ITER shield modules due to plasma disruption.

    SciTech Connect (OSTI)

    Kotulski, Joseph Daniel; Coats, Rebecca Sue; Pasik, Michael Francis; Ulrickson, Michael Andrew

    2009-08-01

    An electromagnetic analysis is performed on the ITER shield modules under different plasma-disruption scenarios using the OPERA-3d software. The models considered include the baseline design as provided by the International Organization and an enhanced design that includes the more realistic geometrical features of a shield module. The modeling procedure is explained, electromagnetic torques are presented, and results of the modeling are discussed.

  19. US ITER is a strong contributor in plan to enhance international sharing of

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    prime ITER real estate | Princeton Plasma Physics Lab US ITER is a strong contributor in plan to enhance international sharing of prime ITER real estate By Lynne Degitz, US ITER March 28, 2013 Tweet Widget Google Plus One Share on Facebook PPPL's Russell Feder, left, and David Johnson developed key features for a modular approach to housing the extensive diagnostic systems that will be installed on the ITER tokamak. (Photo by Elle Starkman/PPPL Office of Communications) PPPL's Russell Feder,

  20. Modeling and Analysis of Alternative Concept of ITER Vacuum Vessel...

    Office of Scientific and Technical Information (OSTI)

    in Google Scholar Search WorldCat Search WorldCat to find libraries that may hold this journal Have feedback or suggestions for a way to improve these results? Save Share...

  1. Momentum space iterative solution of the time-dependent Schrödinger equation

    SciTech Connect (OSTI)

    Kiss, G. Zs.; Borbély, S.; Nagy, L.

    2013-11-13

    We present a novel approach, the iterative solution of the time-dependent Schrödinger equation (iTDSE model), for the investigation of atomic systems interacting with external laser fields. This model is the extension of the momentum-space strong-field approximation (MSSFA) [1], in which the Coulomb potential was considered only as a first order perturbation. In the iTDSE approach higher order terms were gradually introduced until convergence was achieved. Benchmark calculations were done on the hydrogen atom, and the obtained results were compared to the direct numerical solution [2].

  2. Status of research toward the ITER disruption mitigation system

    SciTech Connect (OSTI)

    Hollmann, E. M.; Izzo, V. A.; Aleynikov, P. B.; Lehnen, M.; Snipes, J. A.; Flp, T.; Humphreys, D. A.; Lukash, V. E.; Papp, G.; Pautasso, G.; Saint-Laurent, F.

    2015-02-15

    An overview of the present status of research toward the final design of the ITER disruption mitigation system (DMS) is given. The ITER DMS is based on massive injection of impurities, in order to radiate the plasma stored energy and mitigate the potentially damaging effects of disruptions. The design of this system will be extremely challenging due to many physics and engineering constraints such as limitations on port access and the amount and species of injected impurities. Additionally, many physics questions relevant to the design of the ITER disruption mitigation system remain unsolved such as the mechanisms for mixing and assimilation of injected impurities during the rapid shutdown and the mechanisms for the subsequent formation and dissipation of runaway electron current.

  3. Description of the prototype diagnostic residual gas analyzer for ITER

    SciTech Connect (OSTI)

    Younkin, T. R.; Biewer, T. M.; Klepper, C. C.; Marcus, C.

    2014-11-15

    The diagnostic residual gas analyzer (DRGA) system to be used during ITER tokamak operation is being designed at Oak Ridge National Laboratory to measure fuel ratios (deuterium and tritium), fusion ash (helium), and impurities in the plasma. The eventual purpose of this instrument is for machine protection, basic control, and physics on ITER. Prototyping is ongoing to optimize the hardware setup and measurement capabilities. The DRGA prototype is comprised of a vacuum system and measurement technologies that will overlap to meet ITER measurement requirements. Three technologies included in this diagnostic are a quadrupole mass spectrometer, an ion trap mass spectrometer, and an optical penning gauge that are designed to document relative and absolute gas concentrations.

  4. Is Carbon a Realistic Choice for ITER's Divertor?

    SciTech Connect (OSTI)

    C.H. Skinner; G. Federici

    2005-05-13

    Tritium retention by co-deposition with carbon on the divertor target plate is predicted to limit ITER's DT burning plasma operations (e.g. to about 100 pulses for the worst conditions) before the in-vessel tritium inventory limit, currently set at 350 g, is reached. At this point, ITER will only be able to continue its burning plasma program if technology is available that is capable of rapidly removing large quantities of tritium from the vessel with over 90% efficiency. The removal rate required is four orders of magnitude faster than that demonstrated in current tokamaks. Eighteen years after the observation of co-deposition on JET and TFTR, such technology is nowhere in sight. The inexorable conclusion is that either a major initiative in tritium removal should be funded or that research priorities for ITER should focus on metal alternatives.

  5. Diamond neutral particle spectrometer for fusion reactor ITER

    SciTech Connect (OSTI)

    Krasilnikov, V.; Amosov, V.; Kaschuck, Yu.; Skopintsev, D.

    2014-08-21

    A compact diamond neutral particle spectrometer with digital signal processing has been developed for fast charge-exchange atoms and neutrons measurements at ITER fusion reactor conditions. This spectrometer will play supplementary role for Neutral Particle Analyzer providing 10 ms time and 30 keV energy resolutions for fast particle spectra in non-tritium ITER phase. These data will also be implemented for independent studies of fast ions distribution function evolution in various plasma scenarios with the formation of a single fraction of high-energy ions. In tritium ITER phase the DNPS will measure 14 MeV neutrons spectra. The spectrometer with digital signal processing can operate at peak counting rates reaching a value of 10{sup 6} cps. Diamond neutral particle spectrometer is applicable to future fusion reactors due to its high radiation hardness, fast response and high energy resolution.

  6. Intel C++ compiler error: stl_iterator_base_types.h

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    C++ compiler error: stl_iterator_base_types.h Intel C++ compiler error: stl_iterator_base_types.h December 7, 2015 by Scott French Because the system-supplied version of GCC is relatively old (4.3.4) it is common practice to load the gcc module on our Cray systems when C++11 support is required under the Intel C++ compilers. While this works as expected under the GCC 4.8 and 4.9 series compilers, the 5.x series can cause Intel C++ compile-time errors similar to the following:

  7. Bragg x-ray survey spectrometer for ITER

    SciTech Connect (OSTI)

    Varshney, S. K.; Jakhar, S. [ITER-India, Institute for Plasma Research, Bhat, Gandhinagar, Gujarat 382428 (India); Barnsley, R. [ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance (France); O'Mullane, M. G. [Department of Physics, University of Strathclyde, Glasgow G4 0NG (United Kingdom)

    2012-10-15

    Several potential impurity ions in the ITER plasmas will lead to loss of confined energy through line and continuum emission. For real time monitoring of impurities, a seven channel Bragg x-ray spectrometer (XRCS survey) is considered. This paper presents design and analysis of the spectrometer, including x-ray tracing by the Shadow-XOP code, sensitivity calculations for reference H-mode plasma and neutronics assessment. The XRCS survey performance analysis shows that the ITER measurement requirements of impurity monitoring in 10 ms integration time at the minimum levels for low-Z to high-Z impurity ions can largely be met.

  8. United States Research and Development effort on ITER magnet tasks

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Martovetsky, Nicolai N.; Reierson, Wayne T.

    2011-01-22

    This study presents the status of research and development (R&D) magnet tasks that are being performed in support of the U.S. ITER Project Office (USIPO) commitment to provide a central solenoid assembly and toroidal field conductor for the ITER machine to be constructed in Cadarache, France. The following development tasks are presented: winding development, inlets and outlets development, internal and bus joints development and testing, insulation development and qualification, vacuum-pressure impregnation, bus supports, and intermodule structure and materials characterization.

  9. Visions for Data Management and Remote Collaboration on ITER

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    I P 0.9 MA P IN 2.3 MW H98 1.3 M. Greenwald, et al., APS-DPP November 2007 C-Mod Data Helps Break Covariance Between EFF and nn G Makes Extrapolation To ITER More...

  10. TPA Public Involvement Survey

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Hanford Tri-Party Agencies' Annual Public Involvement Survey Activities for Calendar Year 2008 Nolan Curtis Washington State Department of Ecology Nuclear Waste Program August 5,...

  11. Fusion Materials Science and Technology Research Needs: Now and During the ITER era

    SciTech Connect (OSTI)

    Wirth, Brian D.; Kurtz, Richard J.; Snead, Lance L.

    2013-09-30

    The plasma facing components, first wall and blanket systems of future tokamak-based fusion power plants arguably represent the single greatest materials engineering challenge of all time. Indeed, the United States National Academy of Engineering has recently ranked the quest for fusion as one of the top grand challenges for engineering in the 21st Century. These challenges are even more pronounced by the lack of experimental testing facilities that replicate the extreme operating environment involving simultaneous high heat and particle fluxes, large time varying stresses, corrosive chemical environments, and large fluxes of 14-MeV peaked fusion neutrons. This paper will review, and attempt to prioritize, the materials research and development challenges facing fusion nuclear science and technology into the ITER era and beyond to DEMO. In particular, the presentation will highlight the materials degradation mechanisms we anticipate to occur in the fusion environment, the temperature- displacement goals for fusion materials and plasma facing components and the near and long-term materials challenges required for both ITER, a fusion nuclear science facility and longer term ultimately DEMO.

  12. Atomic data for the ITER Core Imaging X-ray Spectrometer (Conference...

    Office of Scientific and Technical Information (OSTI)

    Atomic data for the ITER Core Imaging X-ray Spectrometer Citation Details In-Document Search Title: Atomic data for the ITER Core Imaging X-ray Spectrometer You are accessing a ...

  13. U.S.Statements on International Fusion Reactor (ITER) Siting Decision |

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Department of Energy U.S.Statements on International Fusion Reactor (ITER) Siting Decision U.S.Statements on International Fusion Reactor (ITER) Siting Decision June 28, 2005 - 1:45pm Addthis WASHINGTON, DC - Today in Moscow, Russia, the ministers representing the six ITER parties, including Dr. Raymond L. Orbach, Director of the U.S. Department of Energy's Office of Science, announced the ITER international fusion reactor will be located at the EU site in Cadarache, France. Below are

  14. Statement of Bernard Bigot Director-General ITER International Fusion Energy Organization

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Bernard Bigot Director-General ITER International Fusion Energy Organization Before the Subcommittee on Energy Committee on Science, Space and Technology U.S House of Representatives The ITER Project: Moving Forward April 20, 2016 Thank you Chairman Weber, Ranking Member Grayson, and distinguished members of the Committee. I am grateful for this opportunity to present to you the status of progress on the ITER Project. Introduction Today we are at a critical time in the history of the ITER

  15. An iterative particle filter approach for coupled hydro-geophysical inversion of a controlled infiltration experiment

    SciTech Connect (OSTI)

    Manoli, Gabriele; Rossi, Matteo; Pasetto, Damiano; Deiana, Rita; Ferraris, Stefano; Cassiani, Giorgio; Putti, Mario

    2015-02-15

    The modeling of unsaturated groundwater flow is affected by a high degree of uncertainty related to both measurement and model errors. Geophysical methods such as Electrical Resistivity Tomography (ERT) can provide useful indirect information on the hydrological processes occurring in the vadose zone. In this paper, we propose and test an iterated particle filter method to solve the coupled hydrogeophysical inverse problem. We focus on an infiltration test monitored by time-lapse ERT and modeled using Richards equation. The goal is to identify hydrological model parameters from ERT electrical potential measurements. Traditional uncoupled inversion relies on the solution of two sequential inverse problems, the first one applied to the ERT measurements, the second one to Richards equation. This approach does not ensure an accurate quantitative description of the physical state, typically violating mass balance. To avoid one of these two inversions and incorporate in the process more physical simulation constraints, we cast the problem within the framework of a SIR (Sequential Importance Resampling) data assimilation approach that uses a Richards equation solver to model the hydrological dynamics and a forward ERT simulator combined with Archie's law to serve as measurement model. ERT observations are then used to update the state of the system as well as to estimate the model parameters and their posterior distribution. The limitations of the traditional sequential Bayesian approach are investigated and an innovative iterative approach is proposed to estimate the model parameters with high accuracy. The numerical properties of the developed algorithm are verified on both homogeneous and heterogeneous synthetic test cases based on a real-world field experiment.

  16. Modeling

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Engine Combustion/Modeling Modelingadmin2015-10-28T01:54:52+00:00 Modelers at the CRF are developing high-fidelity simulation tools for engine combustion and detailed micro-kinetic, surface chemistry modeling tools for catalyst-based exhaust aftertreatment systems. The engine combustion modeling is focused on developing Large Eddy Simulation (LES). LES is being used with closely coupled key target experiments to reveal new understanding of the fundamental processes involved in engine combustion

  17. Advances in the Understanding of ELM Suppression by Resonant Magnetic Perturbations (RMPs) in DIII-D and Implications for ITER

    SciTech Connect (OSTI)

    Nazikian, R.

    2014-09-01

    Experiments on DIII-D have expanding the operating window for RMP ELM suppression to higher q95 with dominant electron heating and fully non-inductive current drive relevant to advanced modes of ITER operation. Robust ELM suppression has also been obtained with a reduced coil set, mitigating the risk of coil failure in maintaining ELM suppression in ITER. These results significantly expand the operating space and reduce risk for obtaining RMP ELM suppression in ITER. Efforts have also been made to search for 3D cause of ELM suppression. No internal non-axisymmetric structure is detected at the top of the pedestal, indicating that the dominant effect of the RMP is to produce an n=0 transport modification of the profiles. Linear two fluid MHD simulations using M3D-C1 indicate resonant field penetration and significant magnetic stochasticity at the top of the pedestal, consistent with the absence of detectable 3D structure in that region. A profile database was developed to compare the scaling of the pedestal and global confinement with the applied 3D field strength in ELM suppressed and ELM mitigated plasmas. The EPED pedestal model accurately predicts the measured pedestal pressure at the threshold of ELM suppression, increasing confidence in theoretical projections to ITER pedestal conditions. Both the H-factor (H(sub)98y2) and thermal energy confinement time do not degrade substantially with applied RMP fields near the threshold of ELM suppression, enhancing confidence in the compatibility of ITER high performance operation with RMP ELM suppression.

  18. ITER movie created by Oak Ridge National Laboratory, National Center for

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Computational Sciences | Princeton Plasma Physics Lab ITER movie created by Oak Ridge National Laboratory, National Center for Computational Sciences American Fusion News Category: U.S. ITER Link: ITER movie created by Oak Ridge National Laboratory, National Center for Computational Sciences

  19. Material migration studies with an ITER first wall panel proxy on EAST

    SciTech Connect (OSTI)

    Ding, R.; Pitts, R. A.; Borodin, D.; Carpentier, S.; Ding, F.; Gong, X. Z.; Guo, H. Y.; Kirschner, A.; Kocan, M.; Li, J. G.; Luo, G. -N.; Mao, H. M.; Qian, J. P.; Stangeby, P. C.; Wampler, W. R.; Wang, H. Q.; Wang, W. Z.; Chen, J. L.; Gan, K. F.

    2015-01-23

    The ITER beryllium (Be) first wall (FW) panels are shaped to protect leading edges between neighbouring panels arising from assembly tolerances. This departure from a perfectly cylindrical surface automatically leads to magnetically shadowed regions where eroded Be can be re-deposited, together with co-deposition of tritium fuel. To provide a benchmark for a series of erosion/re-deposition simulation studies performed for the ITER FW panels, dedicated experiments have been performed on the EAST tokamak using a specially designed, instrumented test limiter acting as a proxy for the FW panel geometry. Carbon coated molybdenum plates forming the limiter front surface were exposed to the outer midplane boundary plasma of helium discharges using the new Material and Plasma Evaluation System (MAPES). Net erosion and deposition patterns are estimated using ion beam analysis to measure the carbon layer thickness variation across the surface after exposure. The highest erosion of about 0.8 µm is found near the midplane, where the surface is closest to the plasma separatrix. No net deposition above the measurement detection limit was found on the proxy wall element, even in shadowed regions. The measured 2D surface erosion distribution has been modelled with the 3D Monte Carlo code ERO, using the local plasma parameter measurements together with a diffusive transport assumption. In conclusion, excellent agreement between the experimentally observed net erosion and the modelled erosion profile has been obtained.

  20. Material migration studies with an ITER first wall panel proxy on EAST

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Ding, R.; Pitts, R. A.; Borodin, D.; Carpentier, S.; Ding, F.; Gong, X. Z.; Guo, H. Y.; Kirschner, A.; Kocan, M.; Li, J. G.; et al

    2015-01-23

    The ITER beryllium (Be) first wall (FW) panels are shaped to protect leading edges between neighbouring panels arising from assembly tolerances. This departure from a perfectly cylindrical surface automatically leads to magnetically shadowed regions where eroded Be can be re-deposited, together with co-deposition of tritium fuel. To provide a benchmark for a series of erosion/re-deposition simulation studies performed for the ITER FW panels, dedicated experiments have been performed on the EAST tokamak using a specially designed, instrumented test limiter acting as a proxy for the FW panel geometry. Carbon coated molybdenum plates forming the limiter front surface were exposed tomore » the outer midplane boundary plasma of helium discharges using the new Material and Plasma Evaluation System (MAPES). Net erosion and deposition patterns are estimated using ion beam analysis to measure the carbon layer thickness variation across the surface after exposure. The highest erosion of about 0.8 µm is found near the midplane, where the surface is closest to the plasma separatrix. No net deposition above the measurement detection limit was found on the proxy wall element, even in shadowed regions. The measured 2D surface erosion distribution has been modelled with the 3D Monte Carlo code ERO, using the local plasma parameter measurements together with a diffusive transport assumption. In conclusion, excellent agreement between the experimentally observed net erosion and the modelled erosion profile has been obtained.« less

  1. Optimization studies of the ITER low field side reflectometer

    SciTech Connect (OSTI)

    Hanson, Gregory R; Wilgen, John B; Bigelow, Tim S; Diem, Stephanie J

    2010-01-01

    Microwave reflectometry will be used on ITER to measure the electron density profile, density fluctuations due to MHD/turbulence, ELM density transients, and as a L-H transition monitor. The ITER low field side (LFS) reflectometer system will measure both core and edge quantities using multiple antenna arrays spanning frequency ranges of 15-155 GHz for the O-mode system and 55-220 GHz for the X-mode system. Optimization studies using the GENRAY ray-tracing code have been done for edge and core measurements. The reflectometer launchers will utilize the HE11 mode launched from circular corrugated waveguide. The launched beams are assumed to be Gaussian with a beam waist diameter of 0.643 times the waveguide diameter. Optimum launcher size and placement are investigated by computing the antenna coupling between launchers, assuming the launched and received beams have a Gaussian beam pattern.

  2. Optimization studies of the ITER low field side reflectometer

    SciTech Connect (OSTI)

    Diem, S. J.; Wilgen, J. B.; Bigelow, T. S.; Hanson, G. R.; Harvey, R. W.; Smirnov, A. P.

    2010-10-15

    Microwave reflectometry will be used on ITER to measure the electron density profile, density fluctuations due to MHD/turbulence, edge localized mode (ELM) density transients, and as an L-H transition monitor. The ITER low field side reflectometer system will measure both core and edge quantities using multiple antenna arrays spanning frequency ranges of 15-155 GHz for the O-mode system and 55-220 GHz for the X-mode system. Optimization studies using the GENRAY ray-tracing code have been done for edge and core measurements. The reflectometer launchers will utilize the HE11 mode launched from circular corrugated waveguide. The launched beams are assumed to be Gaussian with a beam waist diameter of 0.643 times the waveguide diameter. Optimum launcher size and placement are investigated by computing the antenna coupling between launchers, assuming the launched and received beams have a Gaussian beam pattern.

  3. Variable frequency iteration MPPT for resonant power converters

    DOE Patents [OSTI]

    Zhang, Qian; Bataresh, Issa; Chen, Lin

    2015-06-30

    A method of maximum power point tracking (MPPT) uses an MPPT algorithm to determine a switching frequency for a resonant power converter, including initializing by setting an initial boundary frequency range that is divided into initial frequency sub-ranges bounded by initial frequencies including an initial center frequency and first and second initial bounding frequencies. A first iteration includes measuring initial powers at the initial frequencies to determine a maximum power initial frequency that is used to set a first reduced frequency search range centered or bounded by the maximum power initial frequency including at least a first additional bounding frequency. A second iteration includes calculating first and second center frequencies by averaging adjacent frequent values in the first reduced frequency search range and measuring second power values at the first and second center frequencies. The switching frequency is determined from measured power values including the second power values.

  4. Progress and present status of ITER cryoline system

    SciTech Connect (OSTI)

    Badgujar, S.; Bonneton, M.; Chalifour, M.; Forgeas, A.; Serio, L. [ITER Organization, Route de Vinon sur Verdon, 13115 St. Paul lez Durance (France); Sarkar, B.; Shah, N. [ITER-India, Institute for Plasma Research, Bhat, Gandhinagar 382428 (India)

    2014-01-29

    The cryoline system at ITER forms a very complex network localized inside the Tokamak building, on a dedicated plant bridge and in cryoplant areas. The cooling power produced in the cryoplant is distributed via these lines with a total length of about 3.7 km and interconnecting all the cold boxes of the cryogenic system as well as the cold boxes of various clients (magnets, cryopumps and thermal shield). Distinct layouts and polygonal geometry, nuclear safety and confinement requirements, difficult installation and in-service inspection/repair demand very high reliability and availability for the cryolines. The finalization of the building-embedded plates for supporting the lines, before the detailed design, has made this project technologically more challenging. The conceptual design phase has been completed and procurement arrangements have been signed with India, responsible for providing the system of cryolines and warm lines to ITER, as in kind contribution. The prototype test for the design and performance validation has been planned on a representative cryoline section. After describing the basic features and general layout of the ITER cryolines, the paper presents key design requirements, conceptual design approach, progress and status of the cryolines project as well as challenges to build such a complex cryoline system.

  5. Qualification of the Joints for the ITER Central Solenoid

    SciTech Connect (OSTI)

    Martovetsky, N; Berryhill, A; Kenney, S

    2011-09-01

    The ITER Central Solenoid has 36 interpancake joints, 12 bus joints, and 12 feeder joints in the magnet. The joints are required to have resistance below 4 nOhm at 45 kA at 4.5 K. The US ITER Project Office developed two different types of interpancake joints with some variations in details in order to find a better design, qualify the joints, and establish a fabrication process. We built and tested four samples of the sintered joints and two samples with butt-bonded joints (a total of eight joints). Both designs met the specifications. Results of the joint development, test results, and selection of the baseline design are presented and discussed in the paper. The ITER Central Solenoid (CS) consists of six modules. Each module is composed of six wound hexapancakes and one quadrapancake. The multipancakes are connected electrically and hydraulically by in-line interpancake joints. The joints are located at the outside diameter (OD) of the module. Cable in conduit conductor (CICC) high-current joints are critical elements in the CICC magnets. In addition to low resistivity, the CS joints must fit a space envelope equivalent to the regular conductor cross section and must have low hydraulic impedance and enough structural strength to withstand the hoop and compressive forces during operation, including cycling. This paper is the continuation of the work reported on the intermodule joints.

  6. Commitment to Public Involvement

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Create a Sustainable Future » Commitment to Public Involvement Commitment to Public Involvement LANL is committed to our neighbors August 1, 2013 Lab Director McMillan talks with Lab historian Ellen McGhee during Lab tour Lab Director McMillan talks with Lab historian Ellen McGhee during Lab tour RELATED IMAGES http://farm4.staticflickr.com/3815/9442115459_390e5bc841_t.jpg Enlarge http://farm8.staticflickr.com/7111/7650961650_ed1571174f_t.jpg Enlarge

  7. Implementation of an iterative matching scheme for the Kapchinskij-Vladimirskij equations in the WARP code

    SciTech Connect (OSTI)

    Chilton, Sven; Chilton, Sven H.

    2008-07-01

    The WARP code is a robust electrostatic particle-in-cell simulation package used to model charged particle beams with strong space-charge forces. A fundamental operation associated with seeding detailed simulations of a beam transport channel is to generate initial conditions where the beam distribution is matched to the structure of a periodic focusing lattice. This is done by solving for periodic, matched solutions to a coupled set of ODEs called the Kapchinskij-Vladimirskij (KV) envelope equations, which describe the evolution of low-order beam moments subject to applied lattice focusing, space-charge defocusing, and thermal defocusing forces. Recently, an iterative numerical method was developed (Lund, Chilton, and Lee, Efficient computation of matched solutions to the KV envelope equations for periodic focusing lattices, Physical Review Special Topics-Accelerators and Beams 9, 064201 2006) to generate matching conditions in a highly flexible, convergent, and fail-safe manner. This method is extended and implemented in the WARP code as a Python package to vastly ease the setup of detailed simulations. In particular, the Python package accommodates any linear applied lattice focusing functions without skew coupling, and a more general set of beam parameter specifications than its predecessor. Lattice strength iteration tools were added to facilitate the implementation of problems with specific applied focusing strengths.

  8. Investigation of statistical iterative reconstruction for dedicated breast CT

    SciTech Connect (OSTI)

    Makeev, Andrey; Glick, Stephen J.

    2013-08-15

    Purpose: Dedicated breast CT has great potential for improving the detection and diagnosis of breast cancer. Statistical iterative reconstruction (SIR) in dedicated breast CT is a promising alternative to traditional filtered backprojection (FBP). One of the difficulties in using SIR is the presence of free parameters in the algorithm that control the appearance of the resulting image. These parameters require tuning in order to achieve high quality reconstructions. In this study, the authors investigated the penalized maximum likelihood (PML) method with two commonly used types of roughness penalty functions: hyperbolic potential and anisotropic total variation (TV) norm. Reconstructed images were compared with images obtained using standard FBP. Optimal parameters for PML with the hyperbolic prior are reported for the task of detecting microcalcifications embedded in breast tissue.Methods: Computer simulations were used to acquire projections in a half-cone beam geometry. The modeled setup describes a realistic breast CT benchtop system, with an x-ray spectra produced by a point source and an a-Si, CsI:Tl flat-panel detector. A voxelized anthropomorphic breast phantom with 280 ?m microcalcification spheres embedded in it was used to model attenuation properties of the uncompressed woman's breast in a pendant position. The reconstruction of 3D images was performed using the separable paraboloidal surrogates algorithm with ordered subsets. Task performance was assessed with the ideal observer detectability index to determine optimal PML parameters.Results: The authors' findings suggest that there is a preferred range of values of the roughness penalty weight and the edge preservation threshold in the penalized objective function with the hyperbolic potential, which resulted in low noise images with high contrast microcalcifications preserved. In terms of numerical observer detectability index, the PML method with optimal parameters yielded substantially improved performance (by a factor of greater than 10) compared to FBP. The hyperbolic prior was also observed to be superior to the TV norm. A few of the best-performing parameter pairs for the PML method also demonstrated superior performance for various radiation doses. In fact, using PML with certain parameter values results in better images, acquired using 2 mGy dose, than FBP-reconstructed images acquired using 6 mGy dose.Conclusions: A range of optimal free parameters for the PML algorithm with hyperbolic and TV norm-based potentials is presented for the microcalcification detection task, in dedicated breast CT. The reported values can be used as starting values of the free parameters, when SIR techniques are used for image reconstruction. Significant improvement in image quality can be achieved by using PML with optimal combination of parameters, as compared to FBP. Importantly, these results suggest improved detection of microcalcifications can be obtained by using PML with lower radiation dose to the patient, than using FBP with higher dose.

  9. Involvement and Communication Committee.

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Public Involvement and Communication Committee Chair 1 : Liz Mattson 4 , Member Vice Chair 1 : Shannon Cram, Member Committee Members 2 : Shelley Cimon Liz Mattson Alissa Cordner Ken Niles Shannon Cram Ed Pacheco Rob Davis Dan Serres Tom Galioto Jean Vanni Floyd Hodges Steve White Paige Knight Unofficial Committee Members or Other Interested Parties 3 : Earl Fordham Gerry Pollet Paige Knight Steve Hudson 4 Susan Leckband 4 Facilitator: Cathy McCague 4 Agency & Technical Support: Kris Holmes

  10. Pre-Commercial Demonstration of Direct Non-Iterative State Estimator (DNSE+)

    SciTech Connect (OSTI)

    Lelic, Dino

    2015-04-24

    The objective of this DOE co-funded project is to demonstrate functionality and performance of a production-grade Direct Non-iterative State Estimator (DNSE) through its integration with NYPA’s Energy Management System (EMS) and an enhanced Real Time Dynamics Monitoring System (RTDMS) synchrophasor platform from Electric Power Group (EPG). A production-grade DNSE aims to overcome a major obstacle to the operational use of synchrophasor data in Synchro-Phasor Management Systems (SPMS) by providing SPMS applications with a consistent and a complete synchrophasor data foundation in the same way that a traditional EMS State Estimator (SE) provides to EMS applications. Specifically, the DNSE uses synchrophasor measurements and Supervisory Control and Data Acquisition (SCADA) measurements, together with the complete power system model, to simultaneously obtain the complete state of the entire utility’s operating model at rates that are close to the synchrophasor data rates. The full system coverage property is what distinguishes the DNSE from the linear synchrophasor SEs (which cover only parts of the operating model that are visible through synchrophasor measurements), and DNSE differs from traditional EMS SE in that the solution is obtained without iterations, without initial values (hence the “direct” in the name), and at a much higher execution rate. This presentation provides an overview of the project objectives, a brief description of the main tasks including the development work to productize and optimize DNSE from its current MATLAB code base, RTDMS enhancement for interfacing with the DNSE, factory acceptance testing, field installation, testing and demonstration, as well as the current status of the project execution.

  11. Microsoft Word - Second_ ITER Council Press Release.doc | Department of

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Energy Second_ ITER Council Press Release.doc Microsoft Word - Second_ ITER Council Press Release.doc PDF icon Microsoft Word - Second_ ITER Council Press Release.doc More Documents & Publications Before the House Subcommittee on Energy - Committee on Science, Space, and Technology Joint Statement by Energy Ministers of G8, The People's Republic of China, India and The Republic of Korea (June 2008) Joint Statement by Energy Ministers of G8, The People's Republic of China, India and The

  12. ISIS++Reference Guide (Iterative Scalable Implicit Solver in C++) Version 1.1

    SciTech Connect (OSTI)

    Alan B. Williams; Benjamin A. Allan; Kyran D. Mish; Robert L. Clay

    1999-04-01

    ISIS++ (Iterative Scalable Implicit Solver in C++) Version 1.1 is a portable, object-oriented framework for solving sparse linear systems of equations. It includes a collection of Krylov solution methods and preconditioners, as well as both uni-processor (serial) and multi-processor (scalable) matrix and vector classes. Though it was developed to solve systems of equations originating from large-scale, 3-D, finite element analyses, it has application in many other fields. This document supersedes the ISIS++ V1.0 Reference Guide, defines the V1. 1 interface specification, and includes the necessary instructions for building and running ISIS++ v 1.1 on Unix platforms. The interface is presented in annotated header format, along with background on design and implementation considerations. A finite difference modeling example problem is included to demonstrate the overall setup and use.

  13. Iterative image-domain decomposition for dual-energy CT

    SciTech Connect (OSTI)

    Niu, Tianye; Dong, Xue; Petrongolo, Michael; Zhu, Lei

    2014-04-15

    Purpose: Dual energy CT (DECT) imaging plays an important role in advanced imaging applications due to its capability of material decomposition. Direct decomposition via matrix inversion suffers from significant degradation of image signal-to-noise ratios, which reduces clinical values of DECT. Existing denoising algorithms achieve suboptimal performance since they suppress image noise either before or after the decomposition and do not fully explore the noise statistical properties of the decomposition process. In this work, the authors propose an iterative image-domain decomposition method for noise suppression in DECT, using the full variance-covariance matrix of the decomposed images. Methods: The proposed algorithm is formulated in the form of least-square estimation with smoothness regularization. Based on the design principles of a best linear unbiased estimator, the authors include the inverse of the estimated variance-covariance matrix of the decomposed images as the penalty weight in the least-square term. The regularization term enforces the image smoothness by calculating the square sum of neighboring pixel value differences. To retain the boundary sharpness of the decomposed images, the authors detect the edges in the CT images before decomposition. These edge pixels have small weights in the calculation of the regularization term. Distinct from the existing denoising algorithms applied on the images before or after decomposition, the method has an iterative process for noise suppression, with decomposition performed in each iteration. The authors implement the proposed algorithm using a standard conjugate gradient algorithm. The method performance is evaluated using an evaluation phantom (Catphan600) and an anthropomorphic head phantom. The results are compared with those generated using direct matrix inversion with no noise suppression, a denoising method applied on the decomposed images, and an existing algorithm with similar formulation as the proposed method but with an edge-preserving regularization term. Results: On the Catphan phantom, the method maintains the same spatial resolution on the decomposed images as that of the CT images before decomposition (8 pairs/cm) while significantly reducing their noise standard deviation. Compared to that obtained by the direct matrix inversion, the noise standard deviation in the images decomposed by the proposed algorithm is reduced by over 98%. Without considering the noise correlation properties in the formulation, the denoising scheme degrades the spatial resolution to 6 pairs/cm for the same level of noise suppression. Compared to the edge-preserving algorithm, the method achieves better low-contrast detectability. A quantitative study is performed on the contrast-rod slice of Catphan phantom. The proposed method achieves lower electron density measurement error as compared to that by the direct matrix inversion, and significantly reduces the error variation by over 97%. On the head phantom, the method reduces the noise standard deviation of decomposed images by over 97% without blurring the sinus structures. Conclusions: The authors propose an iterative image-domain decomposition method for DECT. The method combines noise suppression and material decomposition into an iterative process and achieves both goals simultaneously. By exploring the full variance-covariance properties of the decomposed images and utilizing the edge predetection, the proposed algorithm shows superior performance on noise suppression with high image spatial resolution and low-contrast detectability.

  14. US ITER is a strong contributor in plan to enhance international...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    systems that will be installed on the ITER tokamak. Gallery: Diagram of an equatorial port plug shows the three vertical diagnostic shield modules with detachable first wall...

  15. PPPL and ITER: Lab teams support the world's largest fusion experiment...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    ITER is designed to demonstrate the scientific and technological feasibility of fusion power by the late 2020s. PPPL provides hardware, fabrication and research and development for ...

  16. A turbulent transport network model in MULTIFLUX coupled with TOUGH2

    SciTech Connect (OSTI)

    Danko, G.; Bahrami, D.; Birkholzer, J.T.

    2011-02-15

    A new numerical method is described for the fully iterated, conjugate solution of two discrete submodels, involving (a) a transport network model for heat, moisture, and airflows in a high-permeability, air-filled cavity; and (b) a variably saturated fractured porous medium. The transport network submodel is an integrated-parameter, computational fluid dynamics solver, describing the thermal-hydrologic transport processes in the flow channel system of the cavity with laminar or turbulent flow and convective heat and mass transport, using MULTIFLUX. The porous medium submodel, using TOUGH2, is a solver for the heat and mass transport in the fractured rock mass. The new model solution extends the application fields of TOUGH2 by integrating it with turbulent flow and transport in a discrete flow network system. We present demonstrational results for a nuclear waste repository application at Yucca Mountain with the most realistic model assumptions and input parameters including the geometrical layout of the nuclear spent fuel and waste with variable heat load for the individual containers. The MULTIFLUX and TOUGH2 model elements are fully iterated, applying a programmed reprocessing of the Numerical Transport Code Functionalization model-element in an automated Outside Balance Iteration loop. The natural, convective airflow field and the heat and mass transport in a representative emplacement drift during postclosure are explicitly solved in the new model. The results demonstrate that the direction and magnitude of the air circulation patterns and all transport modes are strongly affected by the heat and moisture transport processes in the surrounding rock, justifying the need for a coupled, fully iterated model solution such as the one presented in the paper.

  17. Advancing the Physics Basis of Quiescent H-mode through Exploration of ITER Relevant Parameters

    SciTech Connect (OSTI)

    Solomon, W. M.; Burrell, K. H.; Fenstermacher, M. E.; Garofalo, A. M.; Grierson, B. A.; Loarte, A.; McKee, G. R.; Nazikian, R.; Snyder, B. P.

    2014-09-01

    Recent experiments on DIII-D have overcome a long-standing limitation in accessing quiescent H-mode (QH-mode), a high confinement state of the plasma that does not exhibit the explosive instabilities associated with edge localized modes (ELMs). In the past, QH-mode was associated with low density operation, but has now been extended to high normalized densities compatible with operation envisioned for ITER. Through the use of strong shaping, QH-mode plasmas have been maintained at high densities, both absolute (?e ? 7 1019 m3) and normalized Greenwald fraction (?e/?G > 0:7) . In these plasmas, the pedestal can evolve to very high pressures and current as the density is increased. Calculations of the pedestal height and width from the EPED model are quantitatively consistent with the experimental observed evolution with density. The comparison of the dependence of the maximum density threshold for QH-mode with plasma shape help validate the underlying theoretical peeling-ballooning models describing ELM stability. High density QH-mode operation with strong shaping has allowed stable access to a previously predicted regime of very high pedestal dubbed \\Super H-mode". In general, QH-mode is found to achieve ELM-stable operation while maintaining adequate impurity exhaust, due to the enhanced impurity transport from an edge harmonic oscillation, thought to be a saturated kink- peeling mode driven by rotation shear. In addition, the impurity confinement time is not affected by rotation, even though the energy confinement time and measured E ? B shear is observed to increase at low toroidal rotation. Together with demonstrations of high beta, high confinement and low q95 for many energy confinement times, these results suggest QH-mode as a potentially attractive operating scenario for ITER's Q=10 mission.

  18. Flow distribution analysis on the cooling tube network of ITER thermal shield

    SciTech Connect (OSTI)

    Nam, Kwanwoo; Chung, Wooho; Noh, Chang Hyun; Kang, Dong Kwon; Kang, Kyoung-O; Ahn, Hee Jae; Lee, Hyeon Gon

    2014-01-29

    Thermal shield (TS) is to be installed between the vacuum vessel or the cryostat and the magnets in ITER tokamak to reduce the thermal radiation load to the magnets operating at 4.2K. The TS is cooled by pressurized helium gas at the inlet temperature of 80K. The cooling tube is welded on the TS panel surface and the composed flow network of the TS cooling tubes is complex. The flow rate in each panel should be matched to the thermal design value for effective radiation shielding. This paper presents one dimensional analysis on the flow distribution of cooling tube network for the ITER TS. The hydraulic cooling tube network is modeled by an electrical analogy. Only the cooling tube on the TS surface and its connecting pipe from the manifold are considered in the analysis model. Considering the frictional factor and the local loss in the cooling tube, the hydraulic resistance is expressed as a linear function with respect to mass flow rate. Sub-circuits in the TS are analyzed separately because each circuit is controlled by its own control valve independently. It is found that flow rates in some panels are insufficient compared with the design values. In order to improve the flow distribution, two kinds of design modifications are proposed. The first one is to connect the tubes of the adjacent panels. This will increase the resistance of the tube on the panel where the flow rate is excessive. The other design suggestion is that an orifice is installed at the exit of tube routing where the flow rate is to be reduced. The analysis for the design suggestions shows that the flow mal-distribution is improved significantly.

  19. The high-β{sub N} hybrid scenario for ITER and FNSF steady-state missions

    SciTech Connect (OSTI)

    Turco, F.; Petty, C. C.; Luce, T. C.; Carlstrom, T. N.; Van Zeeland, M. A.; Ferron, J. R.; Heidbrink, W.; Carpanese, F.; Holcomb, C. T.

    2015-05-15

    New experiments on DIII-D have demonstrated the steady-state potential of the hybrid scenario, with 1 MA of plasma current driven fully non-inductively and β{sub N} up to 3.7 sustained for ∼3 s (∼1.5 current diffusion time, τ{sub R}, in DIII-D), providing the basis for an attractive option for steady-state operation in ITER and FNSF. Excellent confinement is achieved (H{sub 98y2} ∼ 1.6) without performance limiting tearing modes. The hybrid regime overcomes the need for off-axis current drive efficiency, taking advantage of poloidal magnetic flux pumping that is believed to be the result of a saturated 3/2 tearing mode. This allows for efficient current drive close to the axis, without deleterious sawtooth instabilities. In these experiments, the edge surface loop voltage is driven down to zero for >1 τ{sub R} when the poloidal β is increased above 1.9 at a plasma current of 1.0 MA and the ECH power is increased to 3.2 MW. Stationary operation of hybrid plasmas with all on-axis current drive is sustained at pressures slightly above the ideal no-wall limit, while the calculated ideal with-wall MHD limit is β{sub N} ∼ 4–4.5. Off-axis Neutral Beam Injection (NBI) power has been used to broaden the pressure and current profiles in this scenario, seeking to take advantage of higher predicted kink stability limits and lower values of the tearing stability index Δ′, as calculated by the DCON and PEST3 codes. Results based on measured profiles predict ideal limits at β{sub N} > 4.5, 10% higher than the cases with on-axis NBI. A 0-D model, based on the present confinement, β{sub N} and shape values of the DIII-D hybrid scenario, shows that these plasmas are consistent with the ITER 9 MA, Q = 5 mission and the FNSF 6.7 MA scenario with Q = 3.5. With collisionality and edge safety factor values comparable to those envisioned for ITER and FNSF, the high-β{sub N} hybrid represents an attractive high performance option for the steady-state missions of these devices.

  20. Iterative methods for dose reduction and image enhancement in tomography

    DOE Patents [OSTI]

    Miao, Jianwei; Fahimian, Benjamin Pooya

    2012-09-18

    A system and method for creating a three dimensional cross sectional image of an object by the reconstruction of its projections that have been iteratively refined through modification in object space and Fourier space is disclosed. The invention provides systems and methods for use with any tomographic imaging system that reconstructs an object from its projections. In one embodiment, the invention presents a method to eliminate interpolations present in conventional tomography. The method has been experimentally shown to provide higher resolution and improved image quality parameters over existing approaches. A primary benefit of the method is radiation dose reduction since the invention can produce an image of a desired quality with a fewer number projections than seen with conventional methods.

  1. Development of the bus joint for the ITER Central Solenoid

    SciTech Connect (OSTI)

    Martovetsky, Nicolai N; Irick, David Kim; Kenney, Steven J

    2013-01-01

    The terminations of the Central Solenoid (CS) modules are connected to the bus extensions by joints located outside the CS in the gap between the CS and Torodial Field (TF) assemblies. These joints have very strict space limitations. Low resistance is a common requirement for all ITER joints. In addition, the CS bus joints will experience and must be designed to withstand significant variation in the magnetic field of several tenths of a Tesla per second during initiation of plasma. The joint resistance is specified to be less than 4 nOhm. The joints also have to be soldered in the field and designed with the possibility to be installed and dismantled in order to allow cold testing in the cold test facility. We have developed coaxial joints that meet these requirements and have demonstrated the feasibility to fabricate and assemble them in the vertical configuration. We introduced a coupling cylinder with superconducting strands soldered to the surface of the cable that can be installed in the ITER assembly hall and at the Cold Test Facility. This cylinder serves as a transition area between the CS module and the bus extension. We made two racetrack samples and tested four bus joints in our Joint Test Apparatus. Resistance of the bus joints was measured by a decay method and by a microvoltmeter; the value of the current was measured by the Hall probes. This measurement method was verified in the previous tests. The resistance of the joints varied insignificantly from 1.5 to 2 nOhm. One of the challenges associated with a soldered joint is the inability to use corrosive chemicals that are difficult to clean. This paper describes our development work on cable preparation, chrome removal, compaction, soldering, and final assembly and presents the test results.

  2. Proposal of an Arc Detection Technique Based on RF Measurements for the ITER ICRF Antenna

    SciTech Connect (OSTI)

    Huygen, S.; Dumortier, P.; Durodie, F.; Messiaen, A.; Vervier, M.; Vrancken, M.

    2011-12-23

    RF arc detection is a key operational and safety issue for the ICRF system on ITER. Indeed the high voltages inside the antenna put it at risk of arcing, which could cause substantial damage. This paper describes the various possibilities explored by circuit simulation and the strategy now considered to protect the ITER ICRF antenna from RF arcs.

  3. A Good Neighbor: Community Involvement | NREL

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    A Good Neighbor: Community Involvement At NREL, we are dedicated environmental stewards and are committed to making positive contributions in our community. NREL's main campus is a model for environmental protection and sustainable building practices. Photo of a volunteer at the Foothills Animal Shelter. Charitable Contributions Employees are very involved in the community, giving their time, money, and energy. As staff levels have grown, so have contributions, making NREL Jefferson County's

  4. Iterative reconstruction using a Monte Carlo based system transfer matrix for dedicated breast positron emission tomography

    SciTech Connect (OSTI)

    Saha, Krishnendu; Straus, Kenneth J.; Glick, Stephen J.; Chen, Yu.

    2014-08-28

    To maximize sensitivity, it is desirable that ring Positron Emission Tomography (PET) systems dedicated for imaging the breast have a small bore. Unfortunately, due to parallax error this causes substantial degradation in spatial resolution for objects near the periphery of the breast. In this work, a framework for computing and incorporating an accurate system matrix into iterative reconstruction is presented in an effort to reduce spatial resolution degradation towards the periphery of the breast. The GATE Monte Carlo Simulation software was utilized to accurately model the system matrix for a breast PET system. A strategy for increasing the count statistics in the system matrix computation and for reducing the system element storage space was used by calculating only a subset of matrix elements and then estimating the rest of the elements by using the geometric symmetry of the cylindrical scanner. To implement this strategy, polar voxel basis functions were used to represent the object, resulting in a block-circulant system matrix. Simulation studies using a breast PET scanner model with ring geometry demonstrated improved contrast at 45% reduced noise level and 1.5 to 3 times resolution performance improvement when compared to MLEM reconstruction using a simple line-integral model. The GATE based system matrix reconstruction technique promises to improve resolution and noise performance and reduce image distortion at FOV periphery compared to line-integral based system matrix reconstruction.

  5. Status of the design of the ITER ECE diagnostic

    SciTech Connect (OSTI)

    Taylor, G.; Austin, M. E.; Beno, J. H.; Danani, S.; Feder, R.; Hesler, J. L.; Hubbard, A. E.; Johnson, D. W.; Kumar, R.; Pandya, H. K. B.; Roman, C.; Rowan, W. L.; Udintsev, V.; Vayakis, G.; Walsh, M.; Kubo, S.

    2015-03-12

    In this study, the baseline design for the ITER electron cyclotron emission (ECE) diagnostic has entered the detailed preliminary design phase. Two plasma views are planned, a radial view and an oblique view that is sensitive to distortions in the electron momentum distribution near the average thermal momentum. Both views provide high spatial resolution electron temperature profiles when the momentum distribution remains Maxwellian. The ECE diagnostic system consists of the front-end optics, including two 1000 K calibration sources, in equatorial port plug EP9, the 70-1000 GHz transmission system from the front-end to the diagnostics hall, and the ECE instrumentation in the diagnostics hall. The baseline ECE instrumentation will include two Michelson interferometers that can simultaneously measure ordinary and extraordinary mode ECE from 70 to 1000 GHz, and two heterodyne radiometer systems, covering 122-230 GHz and 244-355 GHz. Significant design challenges include 1) developing highly-reliable 1000 K calibration sources and the associated shutters/mirrors, 2) providing compliant couplings between the front-end optics and the polarization splitter box that accommodate displacements of the vacuum vessel during plasma operations and bake out, 3) protecting components from damage due to stray ECH radiation and other intense millimeter wave emission and 4) providing the low-loss broadband transmission system.

  6. Status of the design of the ITER ECE diagnostic

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Taylor, G.; Austin, M. E.; Beno, J. H.; Danani, S.; Ellis, R. F.; Feder, R.; Hesler, J. L.; Hubbard, A. E.; Johnson, D. W.; Kumar, R.; et al

    2015-03-12

    In this study, the baseline design for the ITER electron cyclotron emission (ECE) diagnostic has entered the detailed preliminary design phase. Two plasma views are planned, a radial view and an oblique view that is sensitive to distortions in the electron momentum distribution near the average thermal momentum. Both views provide high spatial resolution electron temperature profiles when the momentum distribution remains Maxwellian. The ECE diagnostic system consists of the front-end optics, including two 1000 K calibration sources, in equatorial port plug EP9, the 70-1000 GHz transmission system from the front-end to the diagnostics hall, and the ECE instrumentation inmore » the diagnostics hall. The baseline ECE instrumentation will include two Michelson interferometers that can simultaneously measure ordinary and extraordinary mode ECE from 70 to 1000 GHz, and two heterodyne radiometer systems, covering 122-230 GHz and 244-355 GHz. Significant design challenges include 1) developing highly-reliable 1000 K calibration sources and the associated shutters/mirrors, 2) providing compliant couplings between the front-end optics and the polarization splitter box that accommodate displacements of the vacuum vessel during plasma operations and bake out, 3) protecting components from damage due to stray ECH radiation and other intense millimeter wave emission and 4) providing the low-loss broadband transmission system.« less

  7. COLLOQUIUM: Functional capabilities and design of the ITER EC H&CD system |

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Princeton Plasma Physics Lab 17, 2016, 4:15pm to 5:30pm Colloquia MBG Auditorium, PPPL (284 cap.) COLLOQUIUM: Functional capabilities and design of the ITER EC H&CD system Dr. Mark Henderson ITER Organization A 24MW Electron Cyclotron (EC) system operating at 170 GHz and 3600 s pulse length is to be installed on ITER. The EC plant shall deliver 20MW of this power to the plasma for Heating and Current Drive (H&CD) applications. The EC system is designed for plasma initiation, central

  8. Formation and Sustainment of ITPs in ITER with the Baseline Heating Mix

    SciTech Connect (OSTI)

    Francesca M. Poli and Charles Kessel

    2012-12-03

    Plasmas with internal transport barriers (ITBs) are a potential and attractive route to steady-state operation in ITER. These plasmas exhibit radially localized regions of improved con nement with steep pressure gradients in the plasma core, which drive large bootstrap current and generate hollow current pro les and negative shear. This work examines the formation and sustainment of ITBs in ITER with electron cyclotron heating and current drive. It is shown that, with a trade-o of the power delivered to the equatorial and to the upper launcher, the sustainment of steady-state ITBs can be demonstrated in ITER with the baseline heating con guration.

  9. Total-system performance assessment for Yucca Mountain - SNL second iteration (TSPA-1993); Volume 1

    SciTech Connect (OSTI)

    Wilson, M.L.; Gauthier, J.H.; Barnard, R.W.; Barr, G.E.; Dockery, H.A.; Dunn, E.; Eaton, R.R.; Guerin, D.C.; Lu, N.; Martinez, M.J.

    1994-04-01

    Sandia National Laboratories has completed the second iteration of the periodic total-system performance assessments (TSPA-93) for the Yucca Mountain Site Characterization Project (YMP). These analyses estimate the future behavior of a potential repository for high-level nuclear waste at the Yucca Mountain, Nevada, site under consideration by the Department of Energy. TSPA-93 builds upon previous efforts by emphasizing YMP concerns relating to site characterization, design, and regulatory compliance. Scenarios describing expected conditions (aqueous and gaseous transport of contaminants) and low-probability events (human-intrusion drilling and volcanic intrusion) are modeled. The hydrologic processes modeled include estimates of the perturbations to ambient conditions caused by heating of the repository resulting from radioactive decay of the waste. Hydrologic parameters and parameter probability distributions have been derived from available site data. Possible future climate changes are modeled by considering two separate groundwater infiltration conditions: {open_quotes}wet{close_quotes} with a mean flux of 10 mm/yr, and {open_quotes}dry{close_quotes} with a mean flux of 0.5 mm/yr. Two alternative waste-package designs and two alternative repository areal thermal power densities are investigated. One waste package is a thin-wall container emplaced in a vertical borehole, and the second is a container designed with corrosion-resistant and corrosion-allowance walls emplaced horizontally in the drift. Thermal power loadings of 57 kW/acre (the loading specified in the original repository conceptual design) and 114 kW/acre (a loading chosen to investigate effects of a {open_quotes}hot repository{close_quotes}) are considered. TSPA-93 incorporates significant new detailed process modeling, including two- and three-dimensional modeling of thermal effects, groundwater flow in the saturated-zone aquifers, and gas flow in the unsaturated zone.

  10. Final Report on ORDER No. 5312-20110620-JOHNSON-01ITER: Core...

    Office of Scientific and Technical Information (OSTI)

    Design Review Support Citation Details In-Document Search Title: Final Report on ORDER No. 5312-20110620-JOHNSON-01ITER: Core Imaging X-Ray Spectrometer Conceptual Design ...

  11. during the ITER era S.J. Zinkle; J.P. Planchard; R.W. Callis...

    Office of Scientific and Technical Information (OSTI)

    Fusion materials science and technology research opportunities now and during the ITER era S.J. Zinkle; J.P. Planchard; R.W. Callis; C.E. Kessel; P.J. Lee; K.A. McCarty; Various...

  12. ITER (International Thermonuclear Experimental Reactor) shield and blanket work package report

    SciTech Connect (OSTI)

    Not Available

    1988-06-01

    This report summarizes nuclear-related work in support of the US effort for the International Thermonuclear Experimental Reactor (ITER) Study. The purpose of this work was to prepare for the first international ITER workshop devoted to defining a basic ITER concept that will serve as a basis for an indepth conceptual design activity over the next 2-1/2 years. Primary tasks carried out during the past year included: design improvements of the inboard shield developed for the TIBER concept, scoping studies of a variety of tritium breeding blanket options, development of necessary design guidelines and evaluation criteria for the blanket options, further safety considerations related to nuclear components and issues regarding structural materials for an ITER device. 44 refs., 31 figs., 29 tabs.

  13. Final Report on ORDER No. 5312-20110620-JOHNSON-01ITER: Core...

    Office of Scientific and Technical Information (OSTI)

    Core Imaging X-Ray Spectrometer Conceptual Design Review Support Citation Details In-Document Search Title: Final Report on ORDER No. 5312-20110620-JOHNSON-01ITER: Core ...

  14. An adaptive sparse-grid-based iterative ensemble Kalman filter approach for

    Office of Scientific and Technical Information (OSTI)

    parameter field estimation (Journal Article) | SciTech Connect An adaptive sparse-grid-based iterative ensemble Kalman filter approach for parameter field estimation Citation Details In-Document Search Title: An adaptive sparse-grid-based iterative ensemble Kalman filter approach for parameter field estimation Authors: Gunzburger, Max D [1] ; Webster, Clayton G [1] ; Zhang, Guannan [1] + Show Author Affiliations ORNL Publication Date: 2013-01-01 OSTI Identifier: 1096322 DOE Contract Number:

  15. Qualification of the US made conductors for ITER TF magnet system

    SciTech Connect (OSTI)

    Martovetsky, N; Hatfield, D; Miller, J; Bruzzone, P; Stepanov, B; Seber, B

    2009-10-08

    The US Domestic Agency (USDA) is one of the six suppliers of the TF conductor for ITER. In order to qualify conductors according to ITER requirements we prepared several lengths of the CICC and short samples for testing in the SULTAN facility in CRPP, Switzerland. We also fully characterized the strands that were used in these SULTAN samples. Fabrication experience and test results are presented and discussed.

  16. Qualification of the US Made Conductors for ITER TF Magnet System

    SciTech Connect (OSTI)

    Martovetsky, Nicolai N; Hatfield, Daniel R; Miller, John R; Bruzzone, P.; Stepanov, B.; Seber, B.

    2010-01-01

    The US Domestic Agency (USDA) is one of the six suppliers of the TF conductor for ITER. In order to qualify conductors according to ITER requirements we prepared several lengths of the CICC and short samples for testing in the SULTAN facility in CRPP, Switzerland. We also fully characterized the strands that were used in these SULTAN samples. Fabrication experience and test results are presented and discussed.

  17. Unique PPPL-led workshop assesses research crucial to the success of ITER |

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Princeton Plasma Physics Lab Unique PPPL-led workshop assesses research crucial to the success of ITER By John Greenwald July 30, 2013 Tweet Widget Google Plus One Share on Facebook Workshop participants from left: PPPL Director Stewart Prager and Theory Head Amitava Bhattacharjee with David Campbell, director of plasma operations at ITER. (Photo by Elle Starkman/ PPPL Office of Communications) Workshop participants from left: PPPL Director Stewart Prager and Theory Head Amitava

  18. Public Involvement and Communications Committee:

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    purposes only 09.08.15 Excerpt from the HAB Process Manual January 2012 Public Involvement and Communications Committee: Develops Board Advice for the TPA agencies on the...

  19. Public Involvement Committee - Transcribed Flipcharts

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    September 3, 2014 Public Involvement Opportunities * Review of PI materials and agency websites, listservs (use of and purpose of notifications). * CD process - approach to PI...

  20. Public Involvement Committee - Transcribed Flipcharts

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    education materials, including web materials * Evaluate effectiveness of TPA public involvement activities. Page 5 FY2015 Work Plan Ideas * Share innovative approaches to public...

  1. The motional Stark effect diagnostic for ITER using a line-shift approach

    SciTech Connect (OSTI)

    Foley, E. L.; Levinton, F. M.; Yuh, H. Y.; Zakharov, L. E.

    2008-10-15

    The United States has been tasked with the development and implementation of a motional Stark effect (MSE) system on ITER. In the harsh ITER environment, MSE is particularly susceptible to degradation, as it depends on polarimetry, and the polarization reflection properties of surfaces are highly sensitive to thin film effects due to plasma deposition and erosion of a first mirror. Here we present the results of a comprehensive study considering a new MSE-based approach to internal plasma magnetic field measurements for ITER. The proposed method uses the line shifts in the MSE spectrum (MSE-LS) to provide a radial profile of the magnetic field magnitude. To determine the utility of MSE-LS for equilibrium reconstruction, studies were performed using the ESC-ERV code system. A near-term opportunity to test the use of MSE-LS for equilibrium reconstruction is being pursued in the implementation of MSE with laser-induced fluorescence on NSTX. Though the field values and beam energies are very different from ITER, the use of a laser allows precision spectroscopy with a similar ratio of linewidth to line spacing on NSTX as would be achievable with a passive system on ITER. Simulation results for ITER and NSTX are presented, and the relative merits of the traditional line polarization approach and the new line-shift approach are discussed.

  2. Development of a spatially resolving x-ray crystal spectrometer for measurement of ion-temperature (T{sub i}) and rotation-velocity (v) profiles in ITER

    SciTech Connect (OSTI)

    Hill, K. W.; Bitter, M.; Delgado-Aparicio, L.; Johnson, D.; Feder, R.; Beiersdorfer, P.; Dunn, J.; Morris, K.; Wang, E.; Reinke, M.; Podpaly, Y.; Rice, J. E.; Barnsley, R.; O'Mullane, M.; Lee, S. G.

    2010-10-15

    Imaging x-ray crystal spectrometer (XCS) arrays are being developed as a US-ITER activity for Doppler measurement of T{sub i} and v profiles of impurities (W, Kr, and Fe) with {approx}7 cm (a/30) and 10-100 ms resolution in ITER. The imaging XCS, modeled after a prototype instrument on Alcator C-Mod, uses a spherically bent crystal and 2D x-ray detectors to achieve high spectral resolving power (E/dE>6000) horizontally and spatial imaging vertically. Two arrays will measure T{sub i} and both poloidal and toroidal rotation velocity profiles. The measurement of many spatial chords permits tomographic inversion for the inference of local parameters. The instrument design, predictions of performance, and results from C-Mod are presented.

  3. Development of a Spatially Resolving X-Ray Crystal Spectrometer (XCS) for Measurement of Ion-Temperature (Ti) and Rotation-Velocity (v) Profiles in ITER

    SciTech Connect (OSTI)

    Hill, K W; Delgado-Aprico, L; Johnson, D; Feder, R; Beiersdorfer,; Dunn, J; Morris, K; Wang, E; Reinke, M; Podpaly, Y; Rice, J E; Barnsley, R; O'Mullane, M; Lee, S G

    2010-05-21

    Imaging XCS arrays are being developed as a US-ITER activity for Doppler measurement of Ti and v profiles of impurities (W, Kr, Fe) with ~7 cm (a/30) and 10-100 ms resolution in ITER. The imaging XCS, modeled after a PPPL-MIT instrument on Alcator C-Mod, uses a spherically bent crystal and 2d x-ray detectors to achieve high spectral resolving power (E/dE>6000) horizontally and spatial imaging vertically. Two arrays will measure Ti and both poloidal and toroidal rotation velocity profiles. Measurement of many spatial chords permits tomographic inversion for inference of local parameters. The instrument design, predictions of performance, and results from C-Mod will be presented.

  4. FEMCAM Analysis of SULTAN Test Results for ITER Nb3SN Cable-conduit Conductors

    SciTech Connect (OSTI)

    Yuhu Zhai, Pierluigi Bruzzone, Ciro Calzolaio

    2013-03-19

    Performance degradation due to filament fracture of Nb3 Sn cable-in-conduit conductors (CICCs) is a critical issue in large-scale magnet designs such as ITER which is currently being constructed in the South of France. The critical current observed in most SULTAN TF CICC samples is significantly lower than expected and the voltage-current characteristic is seen to have a much broader transition from a single strand to the CICC. Moreover, most conductors exhibit the irreversible degradation due to filament fracture and strain relaxation under electromagnetic cyclic loading. With recent success in monitoring thermal strain distribution and its evolution under the electromagnetic cyclic loading from in situ measurement of critical temperature, we apply FEMCAM which includes strand filament breakage and local current sharing effects to SULTAN tested CICCs to study Nb3 Sn strain sensitivity and irreversible performance degradation. FEMCAM combines the thermal bending effect during cool down and the EM bending effect due to locally accumulating Lorentz force during magnet operation. It also includes strand filament fracture and related local current sharing for the calculation of cable n value. In this paper, we model continuous performance degradation under EM cyclic loading based on strain relaxation and the transition broadening upon cyclic loading to the extreme cases seen in SULTAN test data to better quantify conductor performance degradation.

  5. Design and Analysis of the ITER Vertical Stability Coils

    SciTech Connect (OSTI)

    Peter H. Titus, et. al.

    2012-09-06

    The ITER vertical stability (VS) coils have been developed through the preliminary design phase by Princeton Plasma Physics Laboratory (PPPL). Final design, prototyping and construction will be carried out by the Chinese Participant Team contributing lab, Institute of Plasma Physics, Chinese Academy of Sciences (ASIPP). The VS coils are a part of the in-vessel coil systems which include edge localized mode (ELM) coils as well as the VS coils. An overview of the ELM coils is provided in another paper at this conference. 15 The VS design employs four turns of stainless steel jacketed mineral insulated copper (SSMIC) conductors The mineral insulation is Magnesium Oxide (MgO). Joule and nuclear heat is removed by water flowing at 3 m/s through the hollow copper conductor. A key element in the design is that slightly elevated temperatures in the conductor and its support spine during operation impose compressive stresses that mitigate fatigue damage. Away from joints, and break-outs, conductor thermal stresses are low because of the axisymmetry of the winding (there are no corner bends as in the ELM coils).The 120 degree segment joint, and break-out or terminal regions are designed with similar but imperfect constraint compared with the ring coil portion of the VS. The support for the break-out region is made from a high strength copper alloy, CuCrZr. This is needed to conduct nuclear heat to the actively cooled conductor and to the vessel wall. The support "spine" for the ring coil portion of the VS is 316 stainless steel, held to the vessel with preloaded 718 bolts. Lorentz loads resulting from normal operating loads, disruption loads and loads from disruption currents in the support spine shared with vessel, are applied to the VS coil. The transmission of the Lorentz and thermal expansion loads from the "spine" to the vessel rails is via friction augmented with a restraining "lip" to ensure the coil frictional slip is minimal and acceptable. Stresses in the coil, joints, and break-outs are presented. These are compared with static and fatigue allowables. Design for fatigue is much less demanding than for the ELM coils. A total of 30,000 cycles is required for VS design. Loads on the vessel due to the thermal expansion of the coil and spine are significant. Efforts to reduce these by reducing the cross section of the spine have been made but the vessel still must support loads resulting from restraint of thermal expansion.

  6. Public Involvment Plan - Rifle, Colorado

    Office of Legacy Management (LM)

    4-TAR MAC-GWRIF 7.1 UMTRA Ground Water Project Public Involvement Plan for the Environmental Assessment of Ground Water Compliance at the New and Old Rifle, Colorado, Uranium Mill Tailings Sites May 1999 Prepared by U.S. Department of Energy Grand Junction Office Grand Junction, Colorado Work performed under DOE Contract No. DE-AC13-96GJ87335 Public Involvement Plan for the Rifle UMTRA Sites Page 2 Introduction This Public Involvement Plan is tiered to the Uranium Mill Tailings Remedial Action

  7. Appendix V Public Involvement Plan

    Office of Legacy Management (LM)

    V Public Involvement Plan Revision No.: 6 February 2008 Federal Facility Agreement and Consent Order (FFACO) FFACO, Appendix V February 2008 i FFACO Public Involvement Plan U.S. Department of Energy National Nuclear Security Administration Nevada Site Office Las Vegas, Nevada U.S. Department of Defense Defense Threat Reduction Agency Detachment 1, Nevada Operations Mercury, Nevada U.S. Department of Energy Office of Legacy Management Grand Junction, Colorado FFACO, Appendix V February 2008 ii

  8. Method and apparatus for iterative lysis and extraction of algae

    DOE Patents [OSTI]

    Chew, Geoffrey; Boggs, Tabitha; Dykes, Jr., H. Waite H.; Doherty, Stephen J.

    2015-12-01

    A method and system for processing algae involves the use of an ionic liquid-containing clarified cell lysate to lyse algae cells. The resulting crude cell lysate may be clarified and subsequently used to lyse algae cells. The process may be repeated a number of times before a clarified lysate is separated into lipid and aqueous phases for further processing and/or purification of desired products.

  9. ITER vacuum vessel fabrication plan and cost study (D 68) for the international thermonuclear experimental reactor

    SciTech Connect (OSTI)

    1995-01-01

    ITER Task No. 8, Vacuum Vessel Fabrication Plan and Cost Study (D68), was initiated to assess ITER vacuum vessel fabrication, assembly, and cost. The industrial team of Raytheon Engineers & Constructors and Chicago Bridge & Iron (Raytheon/CB&I) reviewed the current vessel basis and prepared a manufacturing plan, assembly plan, and cost estimate commensurate with the present design. The guidance for the Raytheon/CB&I assessment activities was prepared by the ITER Garching Work Site. This guidance provided in the form of work descriptions, sketches, drawings, and costing guidelines for each of the presently identified vacuum vessel Work Breakdown Structure (WBS) elements was compiled in ITER Garching Joint Work Site Memo (Draft No. 9 - G 15 MD 01 94-17-05 W 1). A copy of this document is provided as Appendix 1 to this report. Additional information and clarifications required for the Raytheon/CB&I assessments were coordinated through the US Home Team (USHT) and its technical representative. Design details considered essential to the Task 8 assessments but not available from the ITER Joint Central Team (JCT) were generated by Raytheon/CB&I and documented accordingly.

  10. Modeling

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Caterpillar, Sandia CRADA Opens Door to Multiple Research Projects Capabilities, Computational Modeling & Simulation, CRF, Materials Science, Modeling, Modeling, Modeling & ...

  11. Radiative Decays Involving Light Scalar Mesons

    SciTech Connect (OSTI)

    Deirdre Black; Masayasu Harada; Joseph Schechter

    2002-09-01

    We present a vector dominance model to describe radiative decays involving the light scalar mesons. Assuming that the light scalar mesons form a nonet this model gives relations among various decay amplitudes of the form S--> gamma gamma, V-->Sgamma and S--> Vgamma, where S and V denote scalar and vector mesons. By comparing with experimental radiative decay rates, including those recently measured for phi--> PP'gamma, we obtain various predictions. We discuss briefly ongoing extensions of the present work in an attempt to describe the radiative phi decay measurements in detail.

  12. Numerical studies of the imaging properties of doubly focussing crystals and their application to ITER

    SciTech Connect (OSTI)

    Bitter, M.; Fraenkel, B.; Hill, K.W.; Hsuan, H.; von Goeler, S. )

    1995-01-01

    Line brightness calculations for the parameters at the International Thermonuclear Experimental Reactor (ITER) and results from recent experiments on the Tokamak Fusion Test Reactor (TFTR) indicate that time-resolved measurements of the central ion temperature and other central plasma parameters should be feasible on ITER with nonperturbing amounts of krypton. Since the measurements will have to be performed in the presence of high fluxes of 14-MeV neutrons from DT-fusion reactions, the size of windows, apertures and x-ray detectors must be as small as possible. Under these conditions, the use of doubly focussing crystals can significantly enhance the signal-to-noise ratio. This paper describes numerical studies of the focussing properties of spherically bent crystals and their application to ITER.

  13. Public Involvement Committee - Transcribed Flipcharts

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    December 10, 2013 100-F 1. Public involvement/mtg in March - How to sequence Board Review with public comment period * Path 1: Could request comment period extension * Path 2: Could request HAB comments considered post comment period * If comment period starts in March, HAB could request to comment in May (advice) Page 1 What might be topics for policy-level discussions? What might be ways, other than meetings, to solicit involvement? What might be useful to present at March Board mtg? Page 2

  14. Final Report on ORDER No. 5312-20110620-JOHNSON-01ITER: Core Imaging X-Ray

    Office of Scientific and Technical Information (OSTI)

    Spectrometer Conceptual Design Review Support (Technical Report) | SciTech Connect Final Report on ORDER No. 5312-20110620-JOHNSON-01ITER: Core Imaging X-Ray Spectrometer Conceptual Design Review Support Citation Details In-Document Search Title: Final Report on ORDER No. 5312-20110620-JOHNSON-01ITER: Core Imaging X-Ray Spectrometer Conceptual Design Review Support Authors: Beiersdorfer, P Publication Date: 2013-09-20 OSTI Identifier: 1097747 Report Number(s): LLNL-SR-644215 DOE Contract

  15. Rich Hawryluk recalls "exciting and challenging" years working on ITER

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    | Princeton Plasma Physics Lab Rich Hawryluk recalls "exciting and challenging" years working on ITER By John Greenwald April 23, 2013 Tweet Widget Google Plus One Share on Facebook Gallery: What is it like to be at the center of ITER, the huge international fusion experiment that is under construction in Cadarache, France? "It's both exciting and challenging," said physicist Rich Hawryluk, who recently returned to PPPL after a two-year stint as deputy director-general

  16. Electromagnetic Analysis For The Design Of ITER Diagnostic Port Plugs During Plasma Disruptions

    SciTech Connect (OSTI)

    Zhai, Y

    2014-03-03

    ITER diagnostic port plugs perform many functions including structural support of diagnostic systems under high electromagnetic loads while allowing for diagnostic access to plasma. The design of diagnotic equatorial port plugs (EPP) are largely driven by electromagnetic loads and associate response of EPP structure during plasma disruptions and VDEs. This paper summarizes results of transient electromagnetic analysis using Opera 3d in support of the design activities for ITER diagnostic EPP. A complete distribution of disruption loads on the Diagnostic First Walls (DFWs). Diagnostic Shield Modules (DSMs) and the EPP structure, as well as impact on the system design integration due to electrical contact among various EPP structural components are discussed.

  17. COLLOQUIUM: DIII-D Explorations of Fusion Science to Prepare for ITER and

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    FNSF | Princeton Plasma Physics Lab December 10, 2013, 11:00am to 12:30pm Colloquia MBG Auditorium COLLOQUIUM: DIII-D Explorations of Fusion Science to Prepare for ITER and FNSF Dr. Richard Buttery General Atomics, DIII-D Presentation: File Presentation Abstract: PDF icon COLL.12.10.13.pdf Recent DIII-D research has provided significant new information for the physics basis of key scientific issues for successful operation of ITER and future steady state fusion tokamaks, including control of

  18. Beyond ITER: Neutral beams for a demonstration fusion reactor (DEMO) (invited)

    SciTech Connect (OSTI)

    McAdams, R.

    2014-02-15

    In the development of magnetically confined fusion as an economically sustainable power source, International Tokamak Experimental Reactor (ITER) is currently under construction. Beyond ITER is the demonstration fusion reactor (DEMO) programme in which the physics and engineering aspects of a future fusion power plant will be demonstrated. DEMO will produce net electrical power. The DEMO programme will be outlined and the role of neutral beams for heating and current drive will be described. In particular, the importance of the efficiency of neutral beam systems in terms of injected neutral beam power compared to wallplug power will be discussed. Options for improving this efficiency including advanced neutralisers and energy recovery are discussed.

  19. Objective assessment of image quality and dose reduction in CT iterative reconstruction

    SciTech Connect (OSTI)

    Vaishnav, J. Y. Jung, W. C.; Popescu, L. M.; Zeng, R.; Myers, K. J.

    2014-07-15

    Purpose: Iterative reconstruction (IR) algorithms have the potential to reduce radiation dose in CT diagnostic imaging. As these algorithms become available on the market, a standardizable method of quantifying the dose reduction that a particular IR method can achieve would be valuable. Such a method would assist manufacturers in making promotional claims about dose reduction, buyers in comparing different devices, physicists in independently validating the claims, and the United States Food and Drug Administration in regulating the labeling of CT devices. However, the nonlinear nature of commercially available IR algorithms poses challenges to objectively assessing image quality, a necessary step in establishing the amount of dose reduction that a given IR algorithm can achieve without compromising that image quality. This review paper seeks to consolidate information relevant to objectively assessing the quality of CT IR images, and thereby measuring the level of dose reduction that a given IR algorithm can achieve. Methods: The authors discuss task-based methods for assessing the quality of CT IR images and evaluating dose reduction. Results: The authors explain and review recent literature on signal detection and localization tasks in CT IR image quality assessment, the design of an appropriate phantom for these tasks, possible choices of observers (including human and model observers), and methods of evaluating observer performance. Conclusions: Standardizing the measurement of dose reduction is a problem of broad interest to the CT community and to public health. A necessary step in the process is the objective assessment of CT image quality, for which various task-based methods may be suitable. This paper attempts to consolidate recent literature that is relevant to the development and implementation of task-based methods for the assessment of CT IR image quality.

  20. Fast Acting Eddy Current Driven Valve for Massive Gas Injection on ITER

    SciTech Connect (OSTI)

    Lyttle, Mark S; Baylor, Larry R; Carmichael, Justin R; Combs, Stephen Kirk; Ericson, Milton Nance; Ezell, N Dianne Bull; Meitner, S. J.; Rasmussen, David A; Warmack, Robert J Bruce; Maruyama, So; Kiss, Gabor

    2015-01-01

    Tokamak plasma disruptions present a significant challenge to ITER as they can result in intense heat flux, large forces from halo and eddy currents, and potential first-wall damage from the generation of multi-MeV runaway electrons. Massive gas injection (MGI) of high Z material using fast acting valves is being explored on existing tokamaks and is planned for ITER as a method to evenly distribute the thermal load of the plasma to prevent melting, control the rate of the current decay to minimize mechanical loads, and to suppress the generation of runaway electrons. A fast acting valve and accompanying power supply have been designed and first test articles produced to meet the requirements for a disruption mitigation system on ITER. The test valve incorporates a flyer plate actuator similar to designs deployed on TEXTOR, ASDEX upgrade, and JET [1 3] of a size useful for ITER with special considerations to mitigate the high mechanical forces developed during actuation due to high background magnetic fields. The valve includes a tip design and all-metal valve stem sealing for compatibility with tritium and high neutron and gamma fluxes.

  1. Amesos2 and Belos: Direct and Iterative Solvers for Large Sparse Linear Systems

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Bavier, Eric; Hoemmen, Mark; Rajamanickam, Sivasankaran; Thornquist, Heidi

    2012-01-01

    Solvers for large sparse linear systems come in two categories: direct and iterative. Amesos2, a package in the Trilinos software project, provides direct methods, and Belos, another Trilinos package, provides iterative methods. Amesos2 offers a common interface to many different sparse matrix factorization codes, and can handle any implementation of sparse matrices and vectors, via an easy-to-extend C++ traits interface. It can also factor matrices whose entries have arbitrary “Scalar” type, enabling extended-precision and mixed-precision algorithms. Belos includes many different iterative methods for solving large sparse linear systems and least-squares problems. Unlike competing iterative solver libraries, Belos completely decouples themore » algorithms from the implementations of the underlying linear algebra objects. This lets Belos exploit the latest hardware without changes to the code. Belos favors algorithms that solve higher-level problems, such as multiple simultaneous linear systems and sequences of related linear systems, faster than standard algorithms. The package also supports extended-precision and mixed-precision algorithms. Together, Amesos2 and Belos form a complete suite of sparse linear solvers.« less

  2. U.S. ITER | Princeton Plasma Physics Lab

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Policy Analysts This page features the most requested EIA reports and features for policy analysts. If you can't find what you're looking for, please contact the EIA Information Center. Featured Links Responses to Congressional and other requests Congressional testimony Analysis papers from Annual Energy Outlook Financial data and analysis Environmental data and analysis National Energy Modeling System (NEMS) documentation Energy in Brief Maps Featured Reports Annual Energy Outlook International

  3. Twin-Screw Extruder Development for the ITER Pellet Injection System

    SciTech Connect (OSTI)

    Meitner, Steven J; Baylor, Larry R; Combs, Stephen Kirk; Fehling, Dan T; McGill, James M; Rasmussen, David A; Leachman, J. W.

    2009-01-01

    The ITER pellet injection system is comprised of devices to form and accelerate pellets, and will be connected to inner wall guide tubes for fueling, and outer wall guide tubes for ELM pacing. An extruder will provide a stream of solid hydrogen isotopes to a secondary section, where pellets are cut and accelerated with a gas gun into the plasma. The ITER pellet injection system is required to provide a plasma fueling rate of 120 Pa-m3/s (900 mbar-L/s) and durations of up to 3000 s. The fueling pellets will be injected at a rate up to 10 Hz and pellets used to trigger ELMs will be injected at higher rates up to 20 Hz. A twin-screw extruder for the ITER pellet injection system is under development at the Oak Ridge National Laboratory. A one-fifth ITER scale prototype has been built and has demonstrated the production of a continuous solid deuterium extrusion. The 27 mm diameter, intermeshed, counter-rotating extruder screws are rotated at a rate up to ?5 rpm. Deuterium gas is pre-cooled and liquefied and solidified in separate extruder barrels. The precooler consists of a deuterium gas filled copper coil suspended in a separate stainless steel vessel containing liquid nitrogen. The liquefier is comprised of a copper barrel connected to a Cryomech AL330 cryocooler, which has a machined helical groove surrounded by a copper jacket, through which the pre-cooled deuterium condenses. The lower extruder barrel is connected to a Cryomech GB-37 cryocooler to solidify the deuterium (at ?15 K) before it is forced through the extruder die. The die forms the extrusion to a 3 mm x 4 mm rectangular cross section. Design improvements have been made to improve the pre-cooler and liquefier heat exchangers, to limit the loss of extrusion through gaps in the screws. This paper will describe the design improvements for the next iteration of the extruder prototype.

  4. HOW YOU CAN BE INVOLVED

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    HOW YOU CAN BE INVOLVED www.youtube.com/hanfordsite www.twitter.com/hanfordsite www.facebook.com/hanfordsite The Hanford Site sits on 586-square-miles of shrub-steppe desert in southeastern Washington state. The site was created in 1943 as part of the Manhattan Project to produce plutonium for nuclear weapons. Between 1943 and 1963, nine nuclear reactors were built along the banks of the Columbia River. By 1988, all nine reactors were shut down. The weapons material production mission ended in

  5. Modeling

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Permalink Wind Generator Modeling Computational Modeling & Simulation, Energy, Energy Surety, Grid Integration, Infrastructure Security, Modeling, Modeling & Analysis, News, News & Events, Renewable Energy, SMART Grid, Systems Analysis, Transmission Grid Integration, Wind Energy Wind Generator Modeling This modular block diagram represents the major components of the generic dynamic wind turbine generator models. Model blocks and parameters are used to represent the different wind

  6. Iterative electromagnetic Born inversion applied to earth conductivity imaging

    SciTech Connect (OSTI)

    Alumbaugh, D.L.

    1993-08-01

    This thesis investigates the use of a fast imaging technique to deduce the spatial conductivity distribution in the earth from low frequency (< 1 MHz), cross well electromagnetic (EM) measurements. The theory embodied in this work is the extension of previous strategies and is based on the Born series approximation to solve both the forward and inverse problem. Nonlinear integral equations are employed to derive the series expansion which accounts for the scattered magnetic fields that are generated by inhomogeneities embedded in either a homogenous or a layered earth. A sinusoidally oscillating, vertically oriented magnetic dipole is employed as a source, and it is assumed that the scattering bodies are azimuthally symmetric about the source dipole axis. The use of this model geometry reduces the 3-D vector problem to a more manageable 2-D scalar form. The validity of the cross well EM method is tested by applying the imaging scheme to two sets of field data. Images of the data collected at the Devine, Texas test site show excellent correlation with the well logs. Unfortunately there is a drift error present in the data that limits the accuracy of the results. A more complete set of data collected at the Richmond field station in Richmond, California demonstrates that cross well EM can be successfully employed to monitor the position of an injected mass of salt water. Both the data and the resulting images clearly indicate the plume migrates toward the north-northwest. The plausibility of these conclusions is verified by applying the imaging code to synthetic data generated by a 3-D sheet model.

  7. Public Involvement and Communications Committee Page 1

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    8, 2012 FINAL MEETING SUMMARY HANFORD ADVISORY BOARD PUBLIC INVOLVEMENT & COMMUNICATIONS COMMITTEE MEETING February 8, 2012 Richland, WA Topics in this Meeting Summary Welcome and Introductions .......................................................................................................................... 1 Update on Timely Public Involvement Topics ............................................................................................. 1 Public Involvement for Technical

  8. Reducing the effects of acoustic heterogeneity with an iterative reconstruction method from experimental data in microwave induced thermoacoustic tomography

    SciTech Connect (OSTI)

    Wang, Jinguo; Zhao, Zhiqin Song, Jian; Chen, Guoping; Nie, Zaiping; Liu, Qing-Huo

    2015-05-15

    Purpose: An iterative reconstruction method has been previously reported by the authors of this paper. However, the iterative reconstruction method was demonstrated by solely using the numerical simulations. It is essential to apply the iterative reconstruction method to practice conditions. The objective of this work is to validate the capability of the iterative reconstruction method for reducing the effects of acoustic heterogeneity with the experimental data in microwave induced thermoacoustic tomography. Methods: Most existing reconstruction methods need to combine the ultrasonic measurement technology to quantitatively measure the velocity distribution of heterogeneity, which increases the system complexity. Different to existing reconstruction methods, the iterative reconstruction method combines time reversal mirror technique, fast marching method, and simultaneous algebraic reconstruction technique to iteratively estimate the velocity distribution of heterogeneous tissue by solely using the measured data. Then, the estimated velocity distribution is used subsequently to reconstruct the highly accurate image of microwave absorption distribution. Experiments that a target placed in an acoustic heterogeneous environment are performed to validate the iterative reconstruction method. Results: By using the estimated velocity distribution, the target in an acoustic heterogeneous environment can be reconstructed with better shape and higher image contrast than targets that are reconstructed with a homogeneous velocity distribution. Conclusions: The distortions caused by the acoustic heterogeneity can be efficiently corrected by utilizing the velocity distribution estimated by the iterative reconstruction method. The advantage of the iterative reconstruction method over the existing correction methods is that it is successful in improving the quality of the image of microwave absorption distribution without increasing the system complexity.

  9. DECONTAMINATION DRESSDOWN AT A TRANSPORTATION ACCIDENT INVOLVING...

    Office of Environmental Management (EM)

    Video User' s Guide DECONTAMINATION DRESSDOWN AT A TRANSPORTATION ACCIDENT INVOLVING ... related to emergency response to a transportation accident involving radioactive material. ...

  10. Community Involvement | Y-12 National Security Complex

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Involvement Community Involvement Y-12 is committed to keeping the community informed in areas of operations, environmental concerns, safety and emergency preparedness. To...

  11. Application of ECH to the study of transport in ITER baseline scenario-like discharges in DIII-D

    SciTech Connect (OSTI)

    Pinsker, R. I.; Austin, M. E.; Ernst, D. R.; Garofalo, A. M.; Grierson, B. A.; Hosea, J. C.; Luce, T. C.; Marinoni, A.; McKee, G. R.; Perkins, R. J.; Petty, C. C.; Porkolab, M.; Rost, J. C.; Schmitz, L.; Solomon, W. M.; Taylor, G.; Turco, F.

    2015-03-12

    Recent DIII-D experiments in the ITER Baseline Scenario (IBS) have shown strong increases in fluctuations and correlated reduction of confinement associated with entering the electron-heating-dominated regime with strong electron cyclotron heating (ECH). The addition of 3.2 MW of 110 GHz EC power deposited at ρ~0.42 to IBS discharges with ~3 MW of neutral beam injection causes large increases in low-k and medium-k turbulent density fluctuations observed with Doppler backscatter (DBS), beam emission spectroscopy (BES) and phase-contrast imaging (PCI) diagnostics, correlated with decreases in the energy, particle, and momentum confinement times. Power balance calculations show the electron heat diffusivity χe increases significantly in the mid-radius region 0.4<ρ<0.8, which is roughly the same region where the DBS and BES diagnostics show the increases in turbulent density fluctuations. Confinement of angular momentum is also reduced during ECH. Studies with the TGYRO transport solver show that the model of turbulent transport embodied in the TGLF code quantitatively reproduces the measured transport in both the neutral beam (NB)-only and in the NB plus EC cases. A simple model of the decrease in toroidal rotation with EC power is set forth, which exhibits a bifurcation in the rotational state of the discharge.

  12. Application of ECH to the study of transport in ITER baseline scenario-like discharges in DIII-D

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Pinsker, R. I.; Austin, M. E.; Ernst, D. R.; Garofalo, A. M.; Grierson, B. A.; Hosea, J. C.; Luce, T. C.; Marinoni, A.; McKee, G. R.; Perkins, R. J.; et al

    2015-03-12

    Recent DIII-D experiments in the ITER Baseline Scenario (IBS) have shown strong increases in fluctuations and correlated reduction of confinement associated with entering the electron-heating-dominated regime with strong electron cyclotron heating (ECH). The addition of 3.2 MW of 110 GHz EC power deposited at ρ~0.42 to IBS discharges with ~3 MW of neutral beam injection causes large increases in low-k and medium-k turbulent density fluctuations observed with Doppler backscatter (DBS), beam emission spectroscopy (BES) and phase-contrast imaging (PCI) diagnostics, correlated with decreases in the energy, particle, and momentum confinement times. Power balance calculations show the electron heat diffusivity χe more » increases significantly in the mid-radius region 0.4<ρ<0.8, which is roughly the same region where the DBS and BES diagnostics show the increases in turbulent density fluctuations. Confinement of angular momentum is also reduced during ECH. Studies with the TGYRO transport solver show that the model of turbulent transport embodied in the TGLF code quantitatively reproduces the measured transport in both the neutral beam (NB)-only and in the NB plus EC cases. A simple model of the decrease in toroidal rotation with EC power is set forth, which exhibits a bifurcation in the rotational state of the discharge.« less

  13. Assessment of database for interaction of tritium with ITER plasma facing materials

    SciTech Connect (OSTI)

    Dolan, T.J.; Anderl, R.A.

    1994-09-01

    The present work surveys recent literature on hydrogen isotope interactions with Be, SS and Inconels, Cu, C, and V, and alloys of Cu and V. The goals are (1) to provide input to the International Thermonuclear Experimental Reactor (ITER) team to help with tritium source term estimates for the Early Safety and Environmental Characterization Study and (2) to provide guidance for planning additional research that will be needed to fill gaps in the present materials database. Properties of diffusivity, solubility, permeability, chemical reactions, Soret effect, recombination coefficient, surface effects, trapping, porosity, layered structures, interfaces, and oxides are considered. Various materials data are tabulated, and a matrix display shows an assessment of the quality of the data available for each main property of each material. Recommendations are made for interim values of diffusivity and solubility to be used, pending further discussion by the ITER community.

  14. Design and Overview of 100 kV Bushing for the DNB Injector of ITER

    SciTech Connect (OSTI)

    Shah, Sejal; Bandyopadhyay, M.; Rotti, C.; Singh, M. J.; Roopesh, G.; Chakraborty, A. K. [ITER-India, Institute for Plasma Research, Gandhinagar-382025, Gujarat (India); Rajesh, S. [ITER-India, Institute for Plasma Research, Gandhinagar-382025, Gujarat (India); Microelectronics and Materials Physics Labs, P.O.Box 4500, FIN-90014 University of Oulu (Finland); Nishad, S.; Srusti, B. [DesignTech Systems Ltd, Banjara Hills, Hyderabad, Andhra Pradesh-500034 (India); Schunke, B.; Hemsworth, R.; Chareyre, J.; Svensson, L. [ITER Organisation, Route de Vinon, CS 90 046, 13067 St. Paul lez Durance Cedex (France)

    2011-09-26

    The 100 kV bushing is one of the most important and technologically challenging Safety Important Class (SIC) components of the Diagnostic Neutral Beam (DNB) injector of ITER. It forms interface between gas insulated electrical transmission line and torus primary vacuum and acts as a vacuum feedthrough of ITER. Design optimization has been carried out to meet the electric and structural requirements based on its classification. Unlike HNB bushing, single stage bushing is designed to provide 100 kV isolation. Finite Element Analysis (FEA) based optimization has been carried out for electrostatic and structural analysis. Manufacturing assembly sequence is studied and presented in this paper. However validation of the same is foreseen from manufacturer.

  15. In-Vessel Coil Material Failure Rate Estimates for ITER Design Use

    SciTech Connect (OSTI)

    L. C. Cadwallader

    2013-01-01

    The ITER international project design teams are working to produce an engineering design for construction of this large tokamak fusion experiment. One of the design issues is ensuring proper control of the fusion plasma. In-vessel magnet coils may be needed for plasma control, especially the control of edge localized modes (ELMs) and plasma vertical stabilization (VS). These coils will be lifetime components that reside inside the ITER vacuum vessel behind the blanket modules. As such, their reliability is an important design issue since access will be time consuming if any type of repair were necessary. The following chapters give the research results and estimates of failure rates for the coil conductor and jacket materials to be used for the in-vessel coils. Copper and CuCrZr conductors, and stainless steel and Inconel jackets are examined.

  16. US ITER (International Thermonuclear Experimental Reactor) shield and blanket design activities

    SciTech Connect (OSTI)

    Baker, C.C.

    1988-08-01

    This paper summarizes nuclear-related work in support of the US effort for the International Thermonuclear Experimental Reactor (ITER) Study. Primary tasks carried out during the past year include design improvements of the inboard shield developed for the TIBER concept, scoping studies of a variety of tritium breeding blanket options, development of necessary design guidelines and evaluation criteria for the blanket options, further safety considerations related to nuclear components, and issues regarding structural materials for an ITER device. The blanket concepts considered are the aqueous/Li salt solution, a water-cooled, solid breeder blanket, a helium-cooled, solid-breeder blanket, a blanket cooled by helium containing lithium-bearing particulates, and a blanket concept based on breeding tritium from He/sup 3/. 1 ref., 2 tabs.

  17. Radiation dose reduction in medical x-ray CT via Fourier-based iterative reconstruction

    SciTech Connect (OSTI)

    Fahimian, Benjamin P.; Zhao Yunzhe; Huang Zhifeng; Fung, Russell; Zhu Chun; Miao Jianwei; Mao Yu; Khatonabadi, Maryam; DeMarco, John J.; McNitt-Gray, Michael F.; Osher, Stanley J.

    2013-03-15

    Purpose: A Fourier-based iterative reconstruction technique, termed Equally Sloped Tomography (EST), is developed in conjunction with advanced mathematical regularization to investigate radiation dose reduction in x-ray CT. The method is experimentally implemented on fan-beam CT and evaluated as a function of imaging dose on a series of image quality phantoms and anonymous pediatric patient data sets. Numerical simulation experiments are also performed to explore the extension of EST to helical cone-beam geometry. Methods: EST is a Fourier based iterative algorithm, which iterates back and forth between real and Fourier space utilizing the algebraically exact pseudopolar fast Fourier transform (PPFFT). In each iteration, physical constraints and mathematical regularization are applied in real space, while the measured data are enforced in Fourier space. The algorithm is automatically terminated when a proposed termination criterion is met. Experimentally, fan-beam projections were acquired by the Siemens z-flying focal spot technology, and subsequently interleaved and rebinned to a pseudopolar grid. Image quality phantoms were scanned at systematically varied mAs settings, reconstructed by EST and conventional reconstruction methods such as filtered back projection (FBP), and quantified using metrics including resolution, signal-to-noise ratios (SNRs), and contrast-to-noise ratios (CNRs). Pediatric data sets were reconstructed at their original acquisition settings and additionally simulated to lower dose settings for comparison and evaluation of the potential for radiation dose reduction. Numerical experiments were conducted to quantify EST and other iterative methods in terms of image quality and computation time. The extension of EST to helical cone-beam CT was implemented by using the advanced single-slice rebinning (ASSR) method. Results: Based on the phantom and pediatric patient fan-beam CT data, it is demonstrated that EST reconstructions with the lowest scanner flux setting of 39 mAs produce comparable image quality, resolution, and contrast relative to FBP with the 140 mAs flux setting. Compared to the algebraic reconstruction technique and the expectation maximization statistical reconstruction algorithm, a significant reduction in computation time is achieved with EST. Finally, numerical experiments on helical cone-beam CT data suggest that the combination of EST and ASSR produces reconstructions with higher image quality and lower noise than the Feldkamp Davis and Kress (FDK) method and the conventional ASSR approach. Conclusions: A Fourier-based iterative method has been applied to the reconstruction of fan-bean CT data with reduced x-ray fluence. This method incorporates advantageous features in both real and Fourier space iterative schemes: using a fast and algebraically exact method to calculate forward projection, enforcing the measured data in Fourier space, and applying physical constraints and flexible regularization in real space. Our results suggest that EST can be utilized for radiation dose reduction in x-ray CT via the readily implementable technique of lowering mAs settings. Numerical experiments further indicate that EST requires less computation time than several other iterative algorithms and can, in principle, be extended to helical cone-beam geometry in combination with the ASSR method.

  18. The ITER pre-compression rings – A first in cryogenic composite technology

    SciTech Connect (OSTI)

    Rajainmaki, Hannu; Fanthome, John; Losasso, Marcello; Rodriguez, Jesus; Evans, David; Diaz, Victor

    2014-01-27

    The ITER Pre-Compression Rings represent one of the heaviest composite structures ever manufactured as a single piece and the largest - the outer diameter will be above 5.5 meters - intended for use in a cryogenic environment. With a cross section of 337 mm × 288 mm, each item will weigh more than 3,000 kg. A development program, based on filament wound and dry wound S2 glass unidirectional fibers, the latter processed by VARTM, was completed on one fifth scale rings, and these materials and techniques were shown to be satisfactory. The paper describes how a technology applied to build up primary structures of European launchers is being accommodated to produce the ITER Pre-Compression Rings, fulfilling its extremely challenging requirements. In addition, we will describe how the structural analysis is correlated with the test results of scaled down rings, as well as how the pre-compression rings’ manufacturing process will be qualified.

  19. Review of the International Thermonuclear Experimental Reactor (ITER) detailed design report

    SciTech Connect (OSTI)

    1997-04-18

    Dr. Martha Krebs, Director, Office of Energy Research at the US Department of Energy (DOE), wrote to the Fusion Energy Sciences Advisory Committee (FESAC), in letters dated September 23 and November 6, 1996, requesting that FESAC review the International Thermonuclear Experimental Reactor (ITER) Detailed Design Report (DDR) and provide its view of the adequacy of the DDR as part of the basis for the United States decision to enter negotiations with the other interested Parties regarding the terms and conditions for an agreement for the construction, operations, exploitation and decommissioning of ITER. The letter from Dr. Krebs, referred to as the Charge Letter, provided context for the review and a set of questions of specific interest.

  20. Vacuum Bellows, Vacuum Piping, Cryogenic Break, and Copper Joint Failure Rate Estimates for ITER Design Use

    SciTech Connect (OSTI)

    L. C. Cadwallader

    2010-06-01

    The ITER international project design teams are working to produce an engineering design in preparation for construction of the International Thermonuclear Experimental Reactor (ITER) tokamak. During the course of this work, questions have arisen in regard to safety barriers and equipment reliability as important facets of system design. The vacuum system designers have asked several questions about the reliability of vacuum bellows and vacuum piping. The vessel design team has asked about the reliability of electrical breaks and copper-copper joints used in cryogenic piping. Research into operating experiences of similar equipment has been performed to determine representative failure rates for these components. The following chapters give the research results and the findings for vacuum system bellows, power plant stainless steel piping (amended to represent vacuum system piping), cryogenic system electrical insulating breaks, and copper joints.

  1. PPPL and ITER: Lab teams support the world's largest fusion experiment

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    with leading-edge ideas and design | Princeton Plasma Physics Lab and ITER: Lab teams support the world's largest fusion experiment with leading-edge ideas and design By John Greenwald May 7, 2013 Tweet Widget Google Plus One Share on Facebook PPPL scientists, engineers, technicians and other specialists contribute to the international project. (Photo by Elle Starkman/ PPPL Office of Communications) PPPL scientists, engineers, technicians and other specialists contribute to the international

  2. Absolutely and uniformly convergent iterative approach to inverse scattering with an infinite radius of convergence

    DOE Patents [OSTI]

    Kouri, Donald J.; Vijay, Amrendra; Zhang, Haiyan; Zhang, Jingfeng; Hoffman, David K.

    2007-05-01

    A method and system for solving the inverse acoustic scattering problem using an iterative approach with consideration of half-off-shell transition matrix elements (near-field) information, where the Volterra inverse series correctly predicts the first two moments of the interaction, while the Fredholm inverse series is correct only for the first moment and that the Volterra approach provides a method for exactly obtaining interactions which can be written as a sum of delta functions.

  3. Effects of coupling and asymmetries on load resilience of IC ITER-like structures

    SciTech Connect (OSTI)

    Bosia, G.; Bremond, S.; Colas, L.

    2005-09-26

    ITER-like structures feature an intrinsic resilience to load variations, which is related to the symmetry of the currents in the two branches of the structure. It has been suggested that the effects of coupling between the array elements would significantly impair the load resilience of the structure. In this paper the effect of inter strap coupling and of however induced electrical array asymmetries on the structure load resilience are quantitatively examined.

  4. Engineering aspects of design and integration of ECE diagnostic in ITER

    SciTech Connect (OSTI)

    Udintsev, V. S.; Taylor, G.; Pandya, H. K.B.; Austin, M. E.; Casal, N.; Catalin, R.; Clough, M.; Cuquel, B.; Dapena, M.; Drevon, J. -M.; Feder, R.; Friconneau, J. P.; Giacomin, T.; Guirao, J.; Henderson, M. A.; Hughes, S.; Iglesias, S.; Johnson, D.; Kumar, Siddhart; Kumar, Vina; Levesy, B.; Loesser, D.; Messineo, M.; Penot, C.; Portalès, M.; Oosterbeek, J. W.; Sirinelli, A; Vacas, C.; Vayakis, G.; Walsh, M. J.; Kubo, S.

    2015-03-12

    ITER ECE diagnostic [1] needs not only to meet measurement requirements, but also to withstand various loads, such as electromagnetic, mechanical, neutronic and thermal, and to be protected from stray ECH radiation at 170 GHz and other millimeter wave emission, like Collective Thomson scattering which is planned to operate at 60 GHz. Same or similar loads will be applied to other millimetre-wave diagnostics [2], located both in-vessel and in-port plugs. These loads must be taken into account throughout the design phases of the ECE and other microwave diagnostics to ensure their structural integrity and maintainability. The integration of microwave diagnostics with other ITER systems is another challenging activity which is currently ongoing through port integration and in-vessel integration work. Port Integration has to address the maintenance and the safety aspects of diagnostics, too. Engineering solutions which are being developed to support and to operate ITER ECE diagnostic, whilst complying with safety and maintenance requirements, are discussed in this paper.

  5. Uncertainty assessment and analysis of ITER in-VV tritium inventory determination

    SciTech Connect (OSTI)

    Cristescu, I. R.; Cristescu, I.; Glugla, M.; Murdoch, D.; Ciattaglia, S.

    2008-07-15

    Tracking of tritium inventories on ITER will be essential to ensure that the safety limits established for the mobilizable tritium inventory in the vacuum vessel are not violated. Tritium will be delivered to the ITER site from outside suppliers. Staring with the tritium imports the value of tritium inventory at ITER site will be known with a certain error that will propagate in time. During plasma operation, shot by shot measurements of the tritium delivered to the Torus and recovered will allow the amount of tritium trapped in the Torus to be computed at the end of the day. A case study for different measuring techniques and several measuring points for the tritium recovered from Torus have been done. An alternative method is to measure overnight the variation in the inventory of the storage and delivery system and the associated error when this method will be employed are presented. In order to reduce the errors on the tritium trapped in-vessel, at certain time intervals a method of global tritium inventory will be performed. The method envisages the transfer of all the mobilizable tritium from the plant and measurement of this inventory in the self-assay beds from the storage and delivery system. Evaluation of the most important sources of error for the tritium trapped in-vessel and means of minimization are eventually presented. (authors)

  6. Engineering aspects of design and integration of ECE diagnostic in ITER

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Udintsev, V. S.; Taylor, G.; Pandya, H. K.B.; Austin, M. E.; Casal, N.; Catalin, R.; Clough, M.; Cuquel, B.; Dapena, M.; Drevon, J. -M.; et al

    2015-03-12

    ITER ECE diagnostic [1] needs not only to meet measurement requirements, but also to withstand various loads, such as electromagnetic, mechanical, neutronic and thermal, and to be protected from stray ECH radiation at 170 GHz and other millimeter wave emission, like Collective Thomson scattering which is planned to operate at 60 GHz. Same or similar loads will be applied to other millimetre-wave diagnostics [2], located both in-vessel and in-port plugs. These loads must be taken into account throughout the design phases of the ECE and other microwave diagnostics to ensure their structural integrity and maintainability. The integration of microwave diagnosticsmore » with other ITER systems is another challenging activity which is currently ongoing through port integration and in-vessel integration work. Port Integration has to address the maintenance and the safety aspects of diagnostics, too. Engineering solutions which are being developed to support and to operate ITER ECE diagnostic, whilst complying with safety and maintenance requirements, are discussed in this paper.« less

  7. Paducah WDA CERCLA Process & Public Involvement

    Broader source: Energy.gov [DOE]

    DOE is committed to fostering meaningful community involvement in environmental remediation decision making at the site.

  8. Report of a technical evaluation panel on the use of beryllium for ITER plasma facing material and blanket breeder material

    SciTech Connect (OSTI)

    Ulrickson, M.A.; Manly, W.D.; Dombrowski, D.E.

    1995-08-01

    Beryllium because of its low atomic number and high thermal conductivity, is a candidate for both ITER first wall and divertor surfaces. This study addresses the following: why beryllium; design requirements for the ITER divertor; beryllium supply and unirradiated physical/mechanical property database; effects of irradiation on beryllium properties; tritium issues; beryllium health and safety; beryllium-coolant interactions and safety; thermal and mechanical tests; plasma erosion of beryllium; recommended beryllium grades for ITER plasma facing components; proposed manufacturing methods to produce beryllium parts for ITER; emerging beryllium materials; proposed inspection and maintenance techniques for beryllium components and coatings; time table and costs; and the importance of integrating materials and manufacturing personnel with designers.

  9. DOE - NNSA/NFO -- EM Public Involvement

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Public Involvement NNSA/NFO Language Options U.S. DOE/NNSA - Nevada Field Office Click to subscribe to NNSS News Public Involvement Public Involvement Outreach Photo An integral component of the Environmental Management Program is the public involvement function. Communication with the public is an essential element in successfully conducting Environmental Management work. Public involvement initiatives include developing and distributing fact sheets, publications, and exhibits as well as

  10. EMERGENCY RESPONSE TO A TRANSPORTATION ACCIDENT INVOLVING RADIOACTIVE...

    Office of Environmental Management (EM)

    ransportation ransportation ransportation ransportation Accident Involving Radioactive Material Accident Involving Radioactive Material Accident Involving Radioactive ...

  11. US ITER

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    exposure at the Commerce Park site. Individuals are not required to wear the blue dosimeter badges at this site. 2.11 Worksite Warning Signs and Labels The typical signs you...

  12. Modeling

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    PVLibMatlab Permalink Gallery Sandia Labs Releases New Version of PVLib Toolbox Modeling, News, Photovoltaic, Solar Sandia Labs Releases New Version of PVLib Toolbox Sandia has released version 1.3 of PVLib, its widely used Matlab toolbox for modeling photovoltaic (PV) power systems. The version 1.3 release includes the following added functions: functions to estimate parameters for popular PV module models, including PVsyst and the CEC '5 parameter' model a new model of the effects of solar

  13. Public Involvement Plan | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Public Involvement Plan Public Involvement Plan Every three years, the Public Involvement Plan is updated, prepared, and published by the U.S. Department of Energy Oak Ridge Office of Environmental Management (DOE-OREM) to communicate to you, as a member of the public, the opportunities you have to participate in decisions and information exchanges regarding the remediation of contaminated areas on the Oak Ridge Site. DOE is committed to fostering meaningful public involvement in all aspects of

  14. Cyber Incidents Involving Control Systems

    SciTech Connect (OSTI)

    Robert J. Turk

    2005-10-01

    The Analysis Function of the US-CERT Control Systems Security Center (CSSC) at the Idaho National Laboratory (INL) has prepared this report to document cyber security incidents for use by the CSSC. The description and analysis of incidents reported herein support three CSSC tasks: establishing a business case; increasing security awareness and private and corporate participation related to enhanced cyber security of control systems; and providing informational material to support model development and prioritize activities for CSSC. The stated mission of CSSC is to reduce vulnerability of critical infrastructure to cyber attack on control systems. As stated in the Incident Management Tool Requirements (August 2005) ''Vulnerability reduction is promoted by risk analysis that tracks actual risk, emphasizes high risk, determines risk reduction as a function of countermeasures, tracks increase of risk due to external influence, and measures success of the vulnerability reduction program''. Process control and Supervisory Control and Data Acquisition (SCADA) systems, with their reliance on proprietary networks and hardware, have long been considered immune to the network attacks that have wreaked so much havoc on corporate information systems. New research indicates this confidence is misplaced--the move to open standards such as Ethernet, Transmission Control Protocol/Internet Protocol, and Web technologies is allowing hackers to take advantage of the control industry's unawareness. Much of the available information about cyber incidents represents a characterization as opposed to an analysis of events. The lack of good analyses reflects an overall weakness in reporting requirements as well as the fact that to date there have been very few serious cyber attacks on control systems. Most companies prefer not to share cyber attack incident data because of potential financial repercussions. Uniform reporting requirements will do much to make this information available to Department of Homeland Security (DHS) and others who require it. This report summarizes the rise in frequency of cyber attacks, describes the perpetrators, and identifies the means of attack. This type of analysis, when used in conjunction with vulnerability analyses, can be used to support a proactive approach to prevent cyber attacks. CSSC will use this document to evolve a standardized approach to incident reporting and analysis. This document will be updated as needed to record additional event analyses and insights regarding incident reporting. This report represents 120 cyber security incidents documented in a number of sources, including: the British Columbia Institute of Technology (BCIT) Industrial Security Incident Database, the 2003 CSI/FBI Computer Crime and Security Survey, the KEMA, Inc., Database, Lawrence Livermore National Laboratory, the Energy Incident Database, the INL Cyber Incident Database, and other open-source data. The National Memorial Institute for the Prevention of Terrorism (MIPT) database was also interrogated but, interestingly, failed to yield any cyber attack incidents. The results of this evaluation indicate that historical evidence provides insight into control system related incidents or failures; however, that the limited available information provides little support to future risk estimates. The documented case history shows that activity has increased significantly since 1988. The majority of incidents come from the Internet by way of opportunistic viruses, Trojans, and worms, but a surprisingly large number are directed acts of sabotage. A substantial number of confirmed, unconfirmed, and potential events that directly or potentially impact control systems worldwide are also identified. Twelve selected cyber incidents are presented at the end of this report as examples of the documented case studies (see Appendix B).

  15. Public Involvement and Communications Committee Page 1

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    11, 2011 FINAL MEETING SUMMARY HANFORD ADVISORY BOARD PUBLIC INVOLVEMENT & COMMUNICATIONS COMMITTEE MEETING October 11, 2011 Richland, WA Topics in this Meeting Summary Welcome and Introductions ............................................................................................................ 1 Draft Advice - Draft Hanford Public Involvement Plan ................................................................ 1 Public Meetings - Draft Hanford Public Involvement Plan

  16. Development of ITER 15 MA ELMy H-mode Inductive Scenario

    SciTech Connect (OSTI)

    Kessel, C. E.; Campbell, D.; Gribov, Y.; Saibene, G.; Ambrosino, G.; Casper, T.; Cavinato, M.; Fujieda, H.; Hawryluk, R.; Horton, L. D.; Kavin, A.; Kharyrutdinov, R.; Koechl, F.; Leuer, J.; Loarte, A.; Lomas, P. J.; Luce, T.; Lukash, V.; Mattei, M.; Nunes, I.; Parail, V.; Polevoi, A.; Portone, A.; Sartori, R.; Sips, A. C.C.; Thomas, P. R.; Welander, A.; Wesley, J.

    2008-10-16

    The poloidal field (PF) coil system on ITER, which provides both feedforward and feedback control of plasma position, shape, and current, is a critical element for achieving mission performance. Analysis of PF capabilities has focused on the 15 MA Q = 10 scenario with a 300-500 s flattop burn phase. The operating space available for the 15 MA ELMy H-mode plasma discharges in ITER and upgrades to the PF coils or associated systems to establish confidence that ITER mission objectives can be reached have been identified. Time dependent self-consistent free-boundary calculations were performed to examine the impact of plasma variability, discharge programming, and plasma disturbances. Based on these calculations a new reference scenario was developed based upon a large bore initial plasma, early divertor transition, low level heating in L-mode, and a late H-mode onset. Equilibrium analyses for this scenario indicate that the original PF coil limitations do not allow low li (<0.8) operation or lower flux states, and the flattop burn durations were predicted to be less than the desired 400 s. This finding motivates the expansion of the operating space, considering several upgrade options to the PF coils. Analysis was also carried out to examine the feedback current reserve required in the CS and PF coils during a series of disturbances and a feasibility assessment of the 17 MA scenario was undertaken. Results of the studies show that the new scenario and modified PF system will allow a wide range of 15 MA 300-500 s operation and more limited but finite 17 MA operation.

  17. TU-F-18A-02: Iterative Image-Domain Decomposition for Dual-Energy CT

    SciTech Connect (OSTI)

    Niu, T; Dong, X; Petrongolo, M; Zhu, L

    2014-06-15

    Purpose: Dual energy CT (DECT) imaging plays an important role in advanced imaging applications due to its material decomposition capability. Direct decomposition via matrix inversion suffers from significant degradation of image signal-to-noise ratios, which reduces clinical value. Existing de-noising algorithms achieve suboptimal performance since they suppress image noise either before or after the decomposition and do not fully explore the noise statistical properties of the decomposition process. We propose an iterative image-domain decomposition method for noise suppression in DECT, using the full variance-covariance matrix of the decomposed images. Methods: The proposed algorithm is formulated in the form of least-square estimation with smoothness regularization. It includes the inverse of the estimated variance-covariance matrix of the decomposed images as the penalty weight in the least-square term. Performance is evaluated using an evaluation phantom (Catphan 600) and an anthropomorphic head phantom. Results are compared to those generated using direct matrix inversion with no noise suppression, a de-noising method applied on the decomposed images, and an existing algorithm with similar formulation but with an edge-preserving regularization term. Results: On the Catphan phantom, our method retains the same spatial resolution as the CT images before decomposition while reducing the noise standard deviation of decomposed images by over 98%. The other methods either degrade spatial resolution or achieve less low-contrast detectability. Also, our method yields lower electron density measurement error than direct matrix inversion and reduces error variation by over 97%. On the head phantom, it reduces the noise standard deviation of decomposed images by over 97% without blurring the sinus structures. Conclusion: We propose an iterative image-domain decomposition method for DECT. The method combines noise suppression and material decomposition into an iterative process and achieves both goals simultaneously. The proposed algorithm shows superior performance on noise suppression with high image spatial resolution and low-contrast detectability. This work is supported by a Varian MRA grant.

  18. Robust parallel iterative solvers for linear and least-squares problems, Final Technical Report

    SciTech Connect (OSTI)

    Saad, Yousef

    2014-01-16

    The primary goal of this project is to study and develop robust iterative methods for solving linear systems of equations and least squares systems. The focus of the Minnesota team is on algorithms development, robustness issues, and on tests and validation of the methods on realistic problems. 1. The project begun with an investigation on how to practically update a preconditioner obtained from an ILU-type factorization, when the coefficient matrix changes. 2. We investigated strategies to improve robustness in parallel preconditioners in a specific case of a PDE with discontinuous coefficients. 3. We explored ways to adapt standard preconditioners for solving linear systems arising from the Helmholtz equation. These are often difficult linear systems to solve by iterative methods. 4. We have also worked on purely theoretical issues related to the analysis of Krylov subspace methods for linear systems. 5. We developed an effective strategy for performing ILU factorizations for the case when the matrix is highly indefinite. The strategy uses shifting in some optimal way. The method was extended to the solution of Helmholtz equations by using complex shifts, yielding very good results in many cases. 6. We addressed the difficult problem of preconditioning sparse systems of equations on GPUs. 7. A by-product of the above work is a software package consisting of an iterative solver library for GPUs based on CUDA. This was made publicly available. It was the first such library that offers complete iterative solvers for GPUs. 8. We considered another form of ILU which blends coarsening techniques from Multigrid with algebraic multilevel methods. 9. We have released a new version on our parallel solver - called pARMS [new version is version 3]. As part of this we have tested the code in complex settings - including the solution of Maxwell and Helmholtz equations and for a problem of crystal growth.10. As an application of polynomial preconditioning we considered the problem of evaluating f(A)v which arises in statistical sampling. 11. As an application to the methods we developed, we tackled the problem of computing the diagonal of the inverse of a matrix. This arises in statistical applications as well as in many applications in physics. We explored probing methods as well as domain-decomposition type methods. 12. A collaboration with researchers from Toulouse, France, considered the important problem of computing the Schur complement in a domain-decomposition approach. 13. We explored new ways of preconditioning linear systems, based on low-rank approximations.

  19. Engineer Russ Feder leads development of diagnostic tools for US ITER as

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    physicist Dave Johnson shifts to part-time work | Princeton Plasma Physics Lab Engineer Russ Feder leads development of diagnostic tools for US ITER as physicist Dave Johnson shifts to part-time work By John Greenwald March 16, 2015 Tweet Widget Google Plus One Share on Facebook Dave Johnson, left, and Russ Feder with design for component of a diagnostic system behind them. (Photo by Elle Starkman/PPPL Office of Communications) Dave Johnson, left, and Russ Feder with design for component of

  20. Engineer Russ Feder leads development of diagnostic tools for US ITER as

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    physicist Dave Johnson shifts to part-time work | Princeton Plasma Physics Lab Engineer Russ Feder leads development of diagnostic tools for US ITER as physicist Dave Johnson shifts to part-time work By John Greenwald March 16, 2015 Tweet Widget Google Plus One Share on Facebook Dave Johnson, left, and Russ Feder with design for component of a diagnostic system behind them. (Photo by Elle Starkman/PPPL Office of Communications) Dave Johnson, left, and Russ Feder with design for component of

  1. Development of the prototype pneumatic transfer system for ITER neutron activation system

    SciTech Connect (OSTI)

    Cheon, M. S.; Seon, C. R.; Pak, S.; Lee, H. G.; Bertalot, L.

    2012-10-15

    The neutron activation system (NAS) measures neutron fluence at the first wall and the total neutron flux from the ITER plasma, providing evaluation of the fusion power for all operational phases. The pneumatic transfer system (PTS) is one of the key components of the NAS for the proper operation of the system, playing a role of transferring encapsulated samples between the capsule loading machine, irradiation stations, counting stations, and disposal bin. For the validation and the optimization of the design, a prototype of the PTS was developed and capsule transfer tests were performed with the developed system.

  2. Source term evaluation for accident transients in the experimental fusion facility ITER

    SciTech Connect (OSTI)

    Virot, F.; Barrachin, M.; Cousin, F.

    2015-03-15

    We have studied the transport and chemical speciation of radio-toxic and toxic species for an event of water ingress in the vacuum vessel of experimental fusion facility ITER with the ASTEC code. In particular our evaluation takes into account an assessed thermodynamic data for the beryllium gaseous species. This study shows that deposited beryllium dusts of atomic Be and Be(OH){sub 2} are formed. It also shows that Be(OT){sub 2} could exist in some conditions in the drain tank. (authors)

  3. "Rip" Perkins, pioneering PPPL physicist and a design leader for ITER,

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    dies at 80 | Princeton Plasma Physics Lab "Rip" Perkins, pioneering PPPL physicist and a design leader for ITER, dies at 80 By John Greenwald August 11, 2014 Tweet Widget Google Plus One Share on Facebook Francis "Rip" Perkins Francis "Rip" Perkins Gallery: "Rip" Perkins, center, as head of the PPPL Theory Department with Wei-li Lee, left, and John Krommes, right. "Rip" Perkins, center, as head of the PPPL Theory Department with Wei-li Lee,

  4. "Rip" Perkins, pioneering PPPL physicist and a design leader for ITER,

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    dies at 80 | Princeton Plasma Physics Lab "Rip" Perkins, pioneering PPPL physicist and a design leader for ITER, dies at 80 By John Greenwald August 11, 2014 Tweet Widget Google Plus One Share on Facebook Francis "Rip" Perkins Francis "Rip" Perkins Gallery: "Rip" Perkins, center, as head of the PPPL Theory Department with Wei-li Lee, left, and John Krommes, right. "Rip" Perkins, center, as head of the PPPL Theory Department with Wei-li Lee,

  5. Note: Readout of a micromechanical magnetometer for the ITER fusion reactor

    SciTech Connect (OSTI)

    Rimminen, H.; Kyynaeraeinen, J.

    2013-05-15

    We present readout instrumentation for a MEMS magnetometer, placed 30 m away from the MEMS element. This is particularly useful when sensing is performed in high-radiation environment, where the semiconductors in the readout cannot survive. High bandwidth transimpedance amplifiers are used to cancel the cable capacitances of several nanofarads. A frequency doubling readout scheme is used for crosstalk elimination. Signal-to-noise ratio in the range of 60 dB was achieved and with sub-percent nonlinearity. The presented instrument is intended for the steady-state magnetic field measurements in the ITER fusion reactor.

  6. X-ray crystal spectrometer upgrade for ITER-like wall experiments at JET

    SciTech Connect (OSTI)

    Shumack, A. E.; Rzadkiewicz, J.; Chernyshova, M.; Czarski, T.; Karpinski, L.; Jakubowska, K.; Scholz, M.; Byszuk, A.; Cieszewski, R.; Kasprowicz, G.; Pozniak, K.; Wojenski, A.; Zabolotny, W.; Dominik, W.; Conway, N. J.; Dalley, S.; Tyrrell, S.; Zastrow, K.-D.; Figueiredo, J. [EFDA-CSU, Culham Science Centre, Abingdon OX14 3DB; Associao EURATOM and others

    2014-11-15

    The high resolution X-Ray crystal spectrometer at the JET tokamak has been upgraded with the main goal of measuring the tungsten impurity concentration. This is important for understanding impurity accumulation in the plasma after installation of the JET ITER-like wall (main chamber: Be, divertor: W). This contribution provides details of the upgraded spectrometer with a focus on the aspects important for spectral analysis and plasma parameter calculation. In particular, we describe the determination of the spectrometer sensitivity: important for impurity concentration determination.

  7. Development of a Twin-Screw D-2 Extruder for the ITER Pellet Injection System

    SciTech Connect (OSTI)

    Meitner, Steven J; Baylor, Larry R; Carbajo, Juan J; Combs, Stephen Kirk; Fehling, Dan T; Foust, Charles R; McFee, Marshall T; McGill, James M; Rasmussen, David A; Sitterson, R G; Sparks, Dennis O; Qualls, A L

    2009-07-01

    A twin-screw extruder for the ITER pellet injection system is under development at the Oak Ridge National Laboratory. The extruder will provide a stream of solid hydrogen isotopes to a secondary section, where pellets are cut and accelerated with single-stage gas gun into the plasma. A one-fifth ITER scale prototype extruder has been built to produce a continuous solid deuterium extrusion. Deuterium gas is precooled and liquefied before being introduced into the extruder. The precooler consists of a copper vessel containing liquid nitrogen surrounded by a deuterium gas filled copper coil. The liquefier is comprised of a copper cylinder connected to a Cryomech AL330 cryocooler, which is surrounded by a copper coil that the precooled deuterium flows through. The lower extruder barrel is connected to a Cryomech GB-37 cryocooler to solidify the deuterium (at approximate to 15 K) before it is forced through the extruder nozzle. A viewport located below the extruder nozzle provides a direct view of the extrusion. A camera is used to document the extrusion quality and duration. A data acquisition system records the extruder temperatures, torque, and speed, upstream, and downstream pressures. This paper will describe the prototype twin-screw extruder and initial extrusion results.

  8. ITER Core Imaging X-Ray Spectrometer Conceptual Design and Performance Assessment - Phase 2

    SciTech Connect (OSTI)

    Beiersdorfer, P; Wen, J; Dunn, J; Morris, K

    2011-01-02

    During Phase 2 of our study of the CIXS conceptual design we have tackled additional important issues that are unique to the ITER environment. These include the thermal control of the crystal and detector enclosures located in an environment with a 100-250 C ambient temperature, tritium containment, and the range of crystal and detector movement based on the need for spectral adjustments and the desire to make measurements of colder plasmas. In addressing these issues we have selected a ''Dewar''-type enclosure for the crystals and detectors. Applying realistic view factors for radiant heat and making allowance for conduction we have made engineering studies of this enclosure and showed that the cooling requirements can be solved and the temperature can be kept sufficiently constant without compromising the specification parameters of the CIXS. We have chosen a minimum 3 mm combined thickness of the six beryllium windows needed in a Dewar-type enclosure and showed that a single window of 0.5 mm thickness satisfies tritium containment requirements. For measuring the temperature in cooler ITER plasmas, we have chosen to use the K-shell lines of Fe24+. Iron is the preferred choice because its radiation can be analyzed with the identical CIXS settings used for analyzing the tungsten radiation, i.e., essentially no adjustments besides a simple crystal rotation need to be made. We have, however, included an xy{theta}-drive motor arrangement in our design for fine adjustments and full rotation of the crystal mounts.

  9. The influence of an ITER-like wall on disruptions at JET

    SciTech Connect (OSTI)

    Vries, P. C. de Hogeweij, G. M. D.; Baruzzo, M.; Murari, A.; Jachmich, S.; Lomas, P. J.; Matthews, G. F.; Ptterich, T.; Vega, J.; Collaboration: JET-EFDA Contributors

    2014-05-15

    In order to preserve the integrity of large tokamaks such as ITER, the number of disruptions has to be limited. JET has operated previously with a low frequency of disruptions (i.e., disruption rate) of 3.4% [P. C. de Vries et al., Nucl. Fusion 51, 053018 (2011)]. The start of operations with the new full-metal ITER-like wall at JET showed a marked rise in the disruption rate to 10%. A full survey was carried out to identify the root causes, the chain-of-events and classifying each disruption, similar to a previous analysis for carbon-wall operations. It showed the improvements made to avoid various disruption classes, but also indicated those disruption types responsible for the enhanced disruption rate. The latter can be mainly attributed to disruptions due to too high core radiation but also due to density control issues and error field locked modes. Detailed technical and physics understanding of disruption causes is essential for devising optimized strategies to avoid or mitigate these events.

  10. The targeted heating and current drive applications for the ITER electron cyclotron system

    SciTech Connect (OSTI)

    Henderson, M.; Darbos, C.; Gandini, F.; Gassmann, T.; Loarte, A.; Omori, T.; Purohit, D.; Saibene, G.; Gagliardi, M.; Farina, D.; Figini, L.; Hanson, G.; Poli, E.; Takahashi, K.

    2015-02-15

    A 24?MW Electron Cyclotron (EC) system operating at 170?GHz and 3600?s pulse length is to be installed on ITER. The EC plant shall deliver 20?MW of this power to the plasma for Heating and Current Drive (H and CD) applications. The EC system is designed for plasma initiation, central heating, current drive, current profile tailoring, and Magneto-hydrodynamic control (in particular, sawteeth and Neo-classical Tearing Mode) in the flat-top phase of the plasma. A preliminary design review was performed in 2012, which identified a need for extended application of the EC system to the plasma ramp-up, flattop, and ramp down phases of ITER plasma pulse. The various functionalities are prioritized based on those applications, which can be uniquely addressed with the EC system in contrast to other H and CD systems. An initial attempt has been developed at prioritizing the allocated H and CD applications for the three scenarios envisioned: ELMy H-mode (15 MA), Hybrid (?12 MA), and Advanced (?9 MA) scenarios. This leads to the finalization of the design requirements for the EC sub-systems.

  11. Modeling

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    WVMinputs-outputs Permalink Gallery Sandia Labs releases wavelet variability model (WVM) Modeling, News, Photovoltaic, Solar Sandia Labs releases wavelet variability model (WVM) When a single solar photovoltaic (PV) module is in full sunlight, then is shaded by a cloud, and is back in full sunlight in a matter of seconds, a sharp dip then increase in power output will result. However, over an entire PV plant, clouds will often uncover some modules even as they cover others, [...] By Andrea

  12. Modeling

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    A rail tank car of the type used to transport crude oil across North America. Recent incidents have raised concerns about the safety of this practice, which the DOE-DOT-sponsored team is investigating. (photo credit: Harvey Henkelmann) Permalink Gallery Expansion of DOE-DOT Tight Oil Research Work Capabilities, Carbon Capture & Storage, Carbon Storage, Energy, Energy Assurance, Energy Assurance, Fuel Options, Infrastructure Assurance, Infrastructure Security, Modeling, Modeling, Modeling

  13. Modeling

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Monte Carlo modeling it was found that for noisy signals with a significant background component, accuracy is improved by fitting the total emission data which includes the...

  14. Modeling

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    ... Renewable Energy, Research & Capabilities, Wind Energy, Wind News|0 Comments Read More ... Energy, Research & Capabilities, Water Power Sandia Modifies Delft3D Turbine Model ...

  15. Public Involvement and Communications Committee Summaries - Hanford...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    05, 2012 Final Attachment 1: Tri-Party Agreement Agencies - Public Involvement Calendar Fiscal Year 2012 - not available Attachment 2: PIC Meeting Transcribed Flip Chart Notes...

  16. Community Involvement and Making a Difference

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    2016 all issues All Issues submit Community Involvement and Making a Difference A personal message from Kurt Steinhaus, Community Programs Director, Los Alamos National...

  17. Public Involvement and Communications Committee Page 1

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    November 2, 2011 FINAL MEETING SUMMARY HANFORD ADVISORY BOARD PUBLIC INVOLVEMENT & COMMUNICATIONS COMMITTEE MEETING November 2, 2011 Kennewick, WA Topics in this Meeting Summary...

  18. Central Plateau Principles Public Involvement Advice DETAILED...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    v0, 12914 Central Plateau Principles Public Involvement Advice DETAILED BACKGROUND Cleanup of Hanford's Central Plateau is expected to take another four decades or longer, and...

  19. Modeling

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    NASA Earth at Night Video EC, Energy, Energy Efficiency, Global, Modeling, News & Events, Solid-State Lighting, Videos NASA Earth at Night Video Have you ever wondered what the ...

  20. Scalable Nonlinear Solvers for Fully Implicit Coupled Nuclear Fuel Modeling. Final Report

    SciTech Connect (OSTI)

    Cai, Xiao-Chuan; Keyes, David; Yang, Chao; Zheng, Xiang; Pernice, Michael

    2014-09-29

    The focus of the project is on the development and customization of some highly scalable domain decomposition based preconditioning techniques for the numerical solution of nonlinear, coupled systems of partial differential equations (PDEs) arising from nuclear fuel simulations. These high-order PDEs represent multiple interacting physical fields (for example, heat conduction, oxygen transport, solid deformation), each is modeled by a certain type of Cahn-Hilliard and/or Allen-Cahn equations. Most existing approaches involve a careful splitting of the fields and the use of field-by-field iterations to obtain a solution of the coupled problem. Such approaches have many advantages such as ease of implementation since only single field solvers are needed, but also exhibit disadvantages. For example, certain nonlinear interactions between the fields may not be fully captured, and for unsteady problems, stable time integration schemes are difficult to design. In addition, when implemented on large scale parallel computers, the sequential nature of the field-by-field iterations substantially reduces the parallel efficiency. To overcome the disadvantages, fully coupled approaches have been investigated in order to obtain full physics simulations.

  1. Design Analysis and Manufacturing Studies for ITER In-Vessel Coils

    SciTech Connect (OSTI)

    Kalish, M.; Heitzenroeder, P.; Neumeyer, C.; Titus, P.; Zhai, Y.; Zatz, I.; Messineo, M.; Gomez, M.; Hause, C.; Daly, E.; Martin, A.; Wu, Y.; Jin, J.; Long, F.; Song, Y.; Wang, Z.; Yun, Zan; Hsiao, J.; Pillsbury, J. R.; Bohm, T.; Sawan, M.; Jiang, NFN

    2014-07-01

    ITER is incorporating two types of In Vessel Coils (IVCs): ELM Coils to mitigate Edge Localized Modes and VS Coils to provide Vertical Stabilization of the plasma. Strong coupling with the plasma is required so that the ELM and VS Coils can meet their performance requirements. Accordingly, the IVCs are in close proximity to the plasma, mounted just behind the Blanket Shield Modules. This location results in a radiation and temperature environment that is severe necessitating new solutions for material selection as well as challenging analysis and design solutions. Fitting the coil systems in between the blanket shield modules and the vacuum vessel leads to difficult integration with diagnostic cabling and cooling water manifolds.

  2. FETI Prime Domain Decomposition base Parallel Iterative Solver Library Ver.1.0

    Energy Science and Technology Software Center (OSTI)

    2003-09-15

    FETI Prime is a library for the iterative solution of linear equations in solid and structural mechanics. The algorithm employs preconditioned conjugate gradients, with a domain decomposition-based preconditioner. The software is written in C++ and is designed for use with massively parallel computers, using MPI. The algorithm is based on the FETI-DP method, with additional capabilities for handling constraint equations, as well as interfacing with the Salinas structural dynamics code and the Finite Element Interfacemore » (FEI) library. Practical Application: FETI Prime is designed for use with finite element-based simulation codes for solid and structural mechanics. The solver uses element matrices, connectivity information, nodal information, and force vectors computed by the host code and provides back the solution to the linear system of equations, to the user specified level of accuracy, The library is compiled with the host code and becomes an integral part of the host code executable.« less

  3. Iterative Monte Carlo analysis of spin-dependent parton distributions

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Sato, Nobuo; Melnitchouk, Wally; Kuhn, Sebastian E.; Ethier, Jacob J.; Accardi, Alberto

    2016-04-05

    We present a comprehensive new global QCD analysis of polarized inclusive deep-inelastic scattering, including the latest high-precision data on longitudinal and transverse polarization asymmetries from Jefferson Lab and elsewhere. The analysis is performed using a new iterative Monte Carlo fitting technique which generates stable fits to polarized parton distribution functions (PDFs) with statistically rigorous uncertainties. Inclusion of the Jefferson Lab data leads to a reduction in the PDF errors for the valence and sea quarks, as well as in the gluon polarization uncertainty at x ≳ 0.1. Furthermore, the study also provides the first determination of the flavor-separated twist-3 PDFsmore » and the d2 moment of the nucleon within a global PDF analysis.« less

  4. Ultralow dose computed tomography attenuation correction for pediatric PET CT using adaptive statistical iterative reconstruction

    SciTech Connect (OSTI)

    Brady, Samuel L.; Shulkin, Barry L.

    2015-02-15

    Purpose: To develop ultralow dose computed tomography (CT) attenuation correction (CTAC) acquisition protocols for pediatric positron emission tomography CT (PET CT). Methods: A GE Discovery 690 PET CT hybrid scanner was used to investigate the change to quantitative PET and CT measurements when operated at ultralow doses (1035 mA s). CT quantitation: noise, low-contrast resolution, and CT numbers for 11 tissue substitutes were analyzed in-phantom. CT quantitation was analyzed to a reduction of 90% volume computed tomography dose index (0.39/3.64; mGy) from baseline. To minimize noise infiltration, 100% adaptive statistical iterative reconstruction (ASiR) was used for CT reconstruction. PET images were reconstructed with the lower-dose CTAC iterations and analyzed for: maximum body weight standardized uptake value (SUV{sub bw}) of various diameter targets (range 837 mm), background uniformity, and spatial resolution. Radiation dose and CTAC noise magnitude were compared for 140 patient examinations (76 post-ASiR implementation) to determine relative dose reduction and noise control. Results: CT numbers were constant to within 10% from the nondose reduced CTAC image for 90% dose reduction. No change in SUV{sub bw}, background percent uniformity, or spatial resolution for PET images reconstructed with CTAC protocols was found down to 90% dose reduction. Patient population effective dose analysis demonstrated relative CTAC dose reductions between 62% and 86% (3.2/8.30.9/6.2). Noise magnitude in dose-reduced patient images increased but was not statistically different from predose-reduced patient images. Conclusions: Using ASiR allowed for aggressive reduction in CT dose with no change in PET reconstructed images while maintaining sufficient image quality for colocalization of hybrid CT anatomy and PET radioisotope uptake.

  5. Evaluation of static mixer flow enhancements for cryogenic viscous compressor prototype for ITER vacuum system

    SciTech Connect (OSTI)

    Duckworth, Robert C.; Baylor, Larry R.; Meitner, Steven J.; Combs, Stephen K.; Ha, Tam; Morrow, Michael; Biewer, T. [Fusion and Materials for Nuclear System Division, Oak Ridge National Laboratory, Oak Ridge (United States); Rasmussen, David A.; Hechler, Michael P. [U.S. ITER Project Office, Oak Ridge National Laboratory, Oak Ridge (United States); Pearce, Robert J. H.; Dremel, Mattias [ITER Organization, 13115 St. Paul-lez-Durance (France); Boissin, J.-C. [Consultant, Grenoble (France)

    2014-01-29

    As part of the U.S. ITER contribution to the vacuum systems for the ITER fusion project, a cryogenic viscous compressor (CVC) is being designed and fabricated to cryopump hydrogenic gases in the torus and neutral beam exhaust streams and to regenerate the collected gases to controlled pressures such that they can be mechanically pumped with controlled flows to the tritium reprocessing facility. One critical element of the CVC design that required additional investigation was the determination of flow rates of the low pressure (up to 1000 Pa) exhaust stream that would allow for complete pumping of hydrogenic gases while permitting trace levels of helium to pass through the CVC to be pumped by conventional vacuum pumps. A sub-scale prototype test facility was utilized to determine the effectiveness of a static mixer pump tube concept, which consisted of a series of rotated twisted elements brazed into a 2-mm thick, 5-cm diameter stainless steel tube. Cold helium gas flow provided by a dewar and helium transfer line was used to cool the exterior of the static mixer pump tube. Deuterium gas was mixed with helium gas through flow controllers at different concentrations while the composition of the exhaust gas was monitored with a Penning gauge and optical spectrometer to determine the effectiveness of the static mixer. It was found that with tube wall temperatures between 6 K and 9 K, the deuterium gas was completely cryopumped and only helium passed through the tube. These results have been used to design the cooling geometry and the static mixer pump tubes in the full-scale CVC prototype.

  6. Benchmarking MELCOR 1.8.2 for ITER Against Recent EVITA Results

    SciTech Connect (OSTI)

    Merrill, Brad J

    2007-11-01

    A version of MELCOR 1.8.2 modified for use in ITER Preliminary Safety Report analyses was validated against recent data from the EVITA facility located in Cadarache, France. EVITA Test Series 7 was used for this study to verify MELCOR’s ability to predict the pressures, temperatures, cryoplate ice mass, and vaccum vessel (VV) condensate mass for test conditions in EVITA that include injections of steam, nitrogen, and water in to the EVITA VV after the walls had been heated to 165 ºC and the cryoplate had been cooled to -193 ºC. In general, the ability of MELCOR to predict the VV pressure and wall temperatures for the steam only and water only injection tests was very good. Predicted ice layer masses where larger than reported for the EVITA cryoplate, in particular for the steam only injection tests (~40% too high), and the predicted condensate masses were less that measured in EVITA. Both of these descrpancies can be explained by ice porosity. The modified MELCOR 1.8.2 over predicts the EVITA VV pressure for the co-injection tests (e.g., steam plus nitrogen, or water plus nitrogen injections) by almost a factor of two. Based on parametric runs that where made by increasing the predicted cryoplate condensation rate, it is believed that this pressure over prediction is a result of an under predicted cryoplate condensation rate. The particulars of this study are documented in this report as well as conclusions about the impact this study has regarding the use of this verions of MELCOR for consequence analyses for ITER safety reports.

  7. Modeling

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    in warm dense matter experiments with diffuse interface methods in the ALE-AMR code Wangyi Liu ∗ , John Barnard, Alex Friedman, Nathan Masters, Aaron Fisher, Velemir Mlaker, Alice Koniges, David Eder † August 4, 2011 Abstract In this paper we describe an implementation of a single-fluid inter- face model in the ALE-AMR code to simulate surface tension effects. The model does not require explicit information on the physical state of the two phases. The only change to the existing fluid

  8. Coupling the Mixed Potential and Radiolysis Models for Used Fuel Degradation

    SciTech Connect (OSTI)

    Buck, Edgar C.; Jerden, James L.; Ebert, William L.; Wittman, Richard S.

    2013-08-30

    The primary purpose of this report is to describe the strategy for coupling three process level models to produce an integrated Used Fuel Degradation Model (FDM). The FDM, which is based on fundamental chemical and physical principals, provides direct calculation of radionuclide source terms for use in repository performance assessments. The G-value for H2O2 production (Gcond) to be used in the Mixed Potential Model (MPM) (H2O2 is the only radiolytic product presently included but others will be added as appropriate) needs to account for intermediate spur reactions. The effects of these intermediate reactions on [H2O2] are accounted for in the Radiolysis Model (RM). This report details methods for applying RM calculations that encompass the effects of these fast interactions on [H2O2] as the solution composition evolves during successive MPM iterations and then represent the steady-state [H2O2] in terms of an effective instantaneous or conditional generation value (Gcond). It is anticipated that the value of Gcond will change slowly as the reaction progresses through several iterations of the MPM as changes in the nature of fuel surface occur. The Gcond values will be calculated with the RM either after several iterations or when concentrations of key reactants reach threshold values determined from previous sensitivity runs. Sensitivity runs with RM indicate significant changes in G-value can occur over narrow composition ranges. The objective of the mixed potential model (MPM) is to calculate the used fuel degradation rates for a wide range of disposal environments to provide the source term radionuclide release rates for generic repository concepts. The fuel degradation rate is calculated for chemical and oxidative dissolution mechanisms using mixed potential theory to account for all relevant redox reactions at the fuel surface, including those involving oxidants produced by solution radiolysis and provided by the radiolysis model (RM). The RM calculates the concentration of species generated at any specific time and location from the surface of the fuel. Several options being considered for coupling the RM and MPM are described in the report. Different options have advantages and disadvantages based on the extent of coding that would be required and the ease of use of the final product.

  9. Application of the Jacobian-Free Newton-Krylov Method to Nonlinear Acceleration of Transport Source Iteration in Slab Geometry

    SciTech Connect (OSTI)

    Dana A. Knoll; H. Park; Kord Smith

    2011-02-01

    The use of the Jacobian-free Newton-Krylov (JFNK) method within the context of nonlinear diffusion acceleration (NDA) of source iteration is explored. The JFNK method is a synergistic combination of Newton's method as the nonlinear solver and Krylov methods as the linear solver. JFNK methods do not form or store the Jacobian matrix, and Newton's method is executed via probing the nonlinear discrete function to approximate the required matrix-vector products. Current application of NDA relies upon a fixed-point, or Picard, iteration to resolve the nonlinearity. We show that the JFNK method can be used to replace this Picard iteration with a Newton iteration. The Picard linearization is retained as a preconditioner. We show that the resulting JFNK-NDA capability provides benefit in some regimes. Furthermore, we study the effects of a two-grid approach, and the required intergrid transfers when the higher-order transport method is solved on a fine mesh compared to the low-order acceleration problem.

  10. The ITER VIS/IR wide angle viewing system: Challenges and on-going R and D

    SciTech Connect (OSTI)

    Travere, J. M.; Aumeunier, M. H.; Joanny, M.; Jouve, M.; Martin, V.; Moncada, V.; Salasca, S.; Marot, L.; Chabaud, D.; Ferme, J. J.; Bremond, F.; Thonnat, M.

    2011-07-01

    The ITER tokamak is the next generation fusion device which will allow studying burning plasma obtained by a Deuterium-Tritium (D-T) fusion reaction during hundreds of seconds. ITER vacuum vessel real-time protection will be mandatory during plasma operation to avoid water leaks and critical plasma facing components degradation. The protection system will be based on a wide angle viewing system (WAVS) composed with 18 visible (VIS) and 18 infrared (IR) cameras covering 80 % of the vacuum vessel which will be one of the major imaging systems of ITER. Compared to protection systems routinely used on current tokamaks and based on imaging (VIS and/or IR), new constraints must be taken into account because of their influence on the system performance: the harsh environment (high neutron flux) and the metallic plasma facing components (both first wall and divertor). In this new demanding context, we have achieved three mandatory R and D studies starting from the understanding of the source of signals by using realistic photonic simulation up to real-time processing strategy taken into account first order optical design constraints to define what type of performance could be reached for ITER vacuum vessel protection. (authors)

  11. Public Involvement and Communications Committee Page 1

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    said he believes the heart of the Plan is in pages 7 to 11. He said the section uses language that is frequently used by the Board, including public involvement for better long...

  12. Public Involvement and Communications Committee Page 1

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    January 13, 2011 FINAL MEETING SUMMARY HANFORD ADVISORY BOARD PUBLIC INVOLVEMENT & COMMUNICATIONS COMMITTEE MEETING January 13, 2011 Richland, WA Topics in this Meeting Summary Welcome and Introductions ............................................................................................................ 1 State of the Site Meetings ............................................................................................................... 2 Open Government Plan Advice

  13. Strategic Public Involvement Products For Review

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Public Involvement Products For Review PIC Discussion September 4, 2013 1 This list is from July 7, 2010 before we had decided on writing advice and is purely for reference for...

  14. Decontamination Dressdown at a Transportation Accident Involving

    Office of Environmental Management (EM)

    Radioactive Material | Department of Energy Decontamination Dressdown at a Transportation Accident Involving Radioactive Material Decontamination Dressdown at a Transportation Accident Involving Radioactive Material The purpose of this User's Guide is to provide instructors with an overview of the key points covered in the video. The Student Handout portion of this Guide is designed to assist the instructor in reviewing those points with students. The Student Handout should be distributed to

  15. FOIASI - Special Inquiry Review of Allegations Involving

    Energy Savers [EERE]

    PotentialMisconduct by a Senior Office of Environmental Management Official | Department of Energy FOIASI - Special Inquiry Review of Allegations Involving PotentialMisconduct by a Senior Office of Environmental Management Official FOIASI - Special Inquiry Review of Allegations Involving PotentialMisconduct by a Senior Office of Environmental Management Official In September 2009, the Office of Inspector General (OIG) received multiple allegations concerning improprieties by a senior

  16. Modeling

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Sandia Co-Hosts "Climate Risk Forum: Bridging Climate Science and Actuarial Practice" This Fall event was a follow-up to a Climate and Environment Program Area meeting with the California governor's office in July. There, the California Insurance Commissioner, Dave Jones, recognized the value of Sandia's climate-impact modeling and analysis work, led by Stephen Conrad (manager of Sandia's Resilience and Regulatory Effects Dept.), and wanted to connect that [...] By

  17. Modeling

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    diffuse interface methods in ALE-AMR code with application in modeling NDCX-II experiments Wangyi Liu 1 , John Barnard 2 , Alex Friedman 2 , Nathan Masters 2 , Aaron Fisher 2 , Alice Koniges 2 , David Eder 2 1 LBNL, USA, 2 LLNL, USA This work was part of the Petascale Initiative in Computational Science at NERSC, supported by the Director, Office of Science, Advanced Scientific Computing Research, of the U.S. Department of Energy under Contract No. DE-AC02-05CH11231. This work was performed

  18. Modeling

    SciTech Connect (OSTI)

    Loth, E.; Tryggvason, G.; Tsuji, Y.; Elghobashi, S. E.; Crowe, Clayton T.; Berlemont, A.; Reeks, M.; Simonin, O.; Frank, Th; Onishi, Yasuo; Van Wachem, B.

    2005-09-01

    Slurry flows occur in many circumstances, including chemical manufacturing processes, pipeline transfer of coal, sand, and minerals; mud flows; and disposal of dredged materials. In this section we discuss slurry flow applications related to radioactive waste management. The Hanford tank waste solids and interstitial liquids will be mixed to form a slurry so it can be pumped out for retrieval and treatment. The waste is very complex chemically and physically. The ARIEL code is used to model the chemical interactions and fluid dynamics of the waste.

  19. Manager`s views of public involvement

    SciTech Connect (OSTI)

    Branch, K.M.; Heerwagen, J.; Bradbury, J.

    1995-12-01

    Four issues commonly form the framework for debates about the acceptability of proposed projects or technologies--the substantive decision or technological choice; the treatment of the community by the proponent organization; the way the decision-making process has been structured and managed; and the status of institutional safeguards and protection. One of the clear messages of cultural theory is that differences in perspectives are a normal and inevitable part of society, and that attempts to resolve differences by persuasion are not likely to work. These findings are useful when considering the goals and possibilities of public involvement as a decision-making tool, and when designing or evaluating public involvement training programs for managers. The research reported here examines the viewpoints and concerns of managers and decision-makers about the four issues identified above, with particular emphasis on their perspectives and concerns about opening decision-making processes to the public and about managers` roles and responsibilities for structuring and managing open decision-making processes. Implications of these findings for public involvement training for managers is also discussed. The data presented in this paper were obtained from face-to-face interviews with managers and decision-makers with experience managing a variety of hazardous waste management decision-making processes. We conducted these interviews in the course of four separate research projects: needs assessments to support the design and development of a public involvement training program for managers; a study of community residents` and managers` perspectives on the chemical stockpile disposal program; an evaluation of the effectiveness of public involvement training for managers in the Department of Energy; and a study to develop indicators of the benefits and costs of public involvement.

  20. NREL: Technology Deployment - Project Development Model

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Project Development Model NREL developed the Project Development Model to evaluate the risks and investment decisions required for successful renewable energy project development. The two-phase iterative model includes elements in project fundamentals and project development based off commercial project development practices supported by tools such as pro formas and checklists. Project Fundamentals or BEPTC(tm) State & Local Energy Data Enter a city and state or zip code in the State and

  1. Magnetostatic focal spot correction for x-ray tubes operating in strong magnetic fields using iterative optimization

    SciTech Connect (OSTI)

    Lillaney, Prasheel; Shin, Mihye; Conolly, Steven M.; Fahrig, Rebecca

    2012-09-15

    Purpose: Combining x-ray fluoroscopy and MR imaging systems for guidance of interventional procedures has become more commonplace. By designing an x-ray tube that is immune to the magnetic fields outside of the MR bore, the two systems can be placed in close proximity to each other. A major obstacle to robust x-ray tube design is correcting for the effects of the magnetic fields on the x-ray tube focal spot. A potential solution is to design active shielding that locally cancels the magnetic fields near the focal spot. Methods: An iterative optimization algorithm is implemented to design resistive active shielding coils that will be placed outside the x-ray tube insert. The optimization procedure attempts to minimize the power consumption of the shielding coils while satisfying magnetic field homogeneity constraints. The algorithm is composed of a linear programming step and a nonlinear programming step that are interleaved with each other. The coil results are verified using a finite element space charge simulation of the electron beam inside the x-ray tube. To alleviate heating concerns an optimized coil solution is derived that includes a neodymium permanent magnet. Any demagnetization of the permanent magnet is calculated prior to solving for the optimized coils. The temperature dynamics of the coil solutions are calculated using a lumped parameter model, which is used to estimate operation times of the coils before temperature failure. Results: For a magnetic field strength of 88 mT, the algorithm solves for coils that consume 588 A/cm{sup 2}. This specific coil geometry can operate for 15 min continuously before reaching temperature failure. By including a neodymium magnet in the design the current density drops to 337 A/cm{sup 2}, which increases the operation time to 59 min. Space charge simulations verify that the coil designs are effective, but for oblique x-ray tube geometries there is still distortion of the focal spot shape along with deflections of approximately 3 mm in the radial and circumferential directions on the anode. Conclusions: Active shielding is an attractive solution for correcting the effects of magnetic fields on the x-ray focal spot. If extremely long fluoroscopic exposure times are required, longer operation times can be achieved by including a permanent magnet with the active shielding design.

  2. Millimeter wave experiment of ITER equatorial EC launcher mock-up

    SciTech Connect (OSTI)

    Takahashi, K.; Oda, Y.; Kajiwara, K.; Kobayashi, N.; Isozaki, M.; Sakamoto, K.; Omori, T.; Henderson, M.

    2014-02-12

    The full-scale mock-up of the equatorial launcher was fabricated in basis of the baseline design to investigate the mm-wave propagation properties of the launcher, the manufacturability, the cooling line management, how to assemble the components and so on. The mock-up consists of one of three mm-wave transmission sets and one of eight waveguide lines can deliver the mm-wave power. The mock-up was connected to the ITER compatible transmission line and the 170GHz gyrotron and the high power experiment was carried out. The measured radiation pattern of the beam at the location of 2.5m away from the EL mock-up shows the successful steering capability of 20?40. It was also revealed that the radiated profile at both steering and fixed focusing mirror agreed with the calculation. The result also suggests that some unwanted modes are included in the radiated beam. Transmission of 0.5MW-0.4sec and of 0.12MW-50sec were also demonstrated.

  3. Performance evaluation approach for the supercritical helium cold circulators of ITER

    SciTech Connect (OSTI)

    Vaghela, H.; Sarkar, B.; Bhattacharya, R.; Kapoor, H. [ITER-India, Institute for Plasma Research, Near Indira Bridge, Bhat, Gandhinagar-382428 (India); Chalifour, M.; Chang, H.-S.; Serio, L. [ITER Organization, Route de Vinon sur Verdon - 13115 St Paul Lez Durance (France)

    2014-01-29

    The ITER project design foresees Supercritical Helium (SHe) forced flow cooling for the main cryogenic components, namely, the superconducting (SC) magnets and cryopumps (CP). Therefore, cold circulators have been selected to provide the required SHe mass flow rate to cope with specific operating conditions and technical requirements. Considering the availability impacts of such machines, it has been decided to perform evaluation tests of the cold circulators at operating conditions prior to the series production in order to minimize the project technical risks. A proposal has been conceptualized, evaluated and simulated to perform representative tests of the full scale SHe cold circulators. The objectives of the performance tests include the validation of normal operating condition, transient and off-design operating modes as well as the efficiency measurement. A suitable process and instrumentation diagram of the test valve box (TVB) has been developed to implement the tests at the required thermodynamic conditions. The conceptual engineering design of the TVB has been developed along with the required thermal analysis for the normal operating conditions to support the performance evaluation of the SHe cold circulator.

  4. Wide-angle ITER-prototype tangential infrared and visible viewing system for DIII-D

    SciTech Connect (OSTI)

    Lasnier, C. J. Allen, S. L.; Ellis, R. E.; Fenstermacher, M. E.; McLean, A. G.; Meyer, W. H.; Morris, K.; Seppala, L. G.; Crabtree, K.; Van Zeeland, M. A.

    2014-11-15

    An imaging system with a wide-angle tangential view of the full poloidal cross-section of the tokamak in simultaneous infrared and visible light has been installed on DIII-D. The optical train includes three polished stainless steel mirrors in vacuum, which view the tokamak through an aperture in the first mirror, similar to the design concept proposed for ITER. A dichroic beam splitter outside the vacuum separates visible and infrared (IR) light. Spatial calibration is accomplished by warping a CAD-rendered image to align with landmarks in a data image. The IR camera provides scrape-off layer heat flux profile deposition features in diverted and inner-wall-limited plasmas, such as heat flux reduction in pumped radiative divertor shots. Demonstration of the system to date includes observation of fast-ion losses to the outer wall during neutral beam injection, and shows reduced peak wall heat loading with disruption mitigation by injection of a massive gas puff.

  5. Iterative optimizing quantization method for reconstructing three-dimensional images from a limited number of views

    DOE Patents [OSTI]

    Lee, Heung-Rae

    1997-01-01

    A three-dimensional image reconstruction method comprises treating the object of interest as a group of elements with a size that is determined by the resolution of the projection data, e.g., as determined by the size of each pixel. One of the projections is used as a reference projection. A fictitious object is arbitrarily defined that is constrained by such reference projection. The method modifies the known structure of the fictitious object by comparing and optimizing its four projections to those of the unknown structure of the real object and continues to iterate until the optimization is limited by the residual sum of background noise. The method is composed of several sub-processes that acquire four projections from the real data and the fictitious object: generate an arbitrary distribution to define the fictitious object, optimize the four projections, generate a new distribution for the fictitious object, and enhance the reconstructed image. The sub-process for the acquisition of the four projections from the input real data is simply the function of acquiring the four projections from the data of the transmitted intensity. The transmitted intensity represents the density distribution, that is, the distribution of absorption coefficients through the object.

  6. Iterative optimizing quantization method for reconstructing three-dimensional images from a limited number of views

    DOE Patents [OSTI]

    Lee, H.R.

    1997-11-18

    A three-dimensional image reconstruction method comprises treating the object of interest as a group of elements with a size that is determined by the resolution of the projection data, e.g., as determined by the size of each pixel. One of the projections is used as a reference projection. A fictitious object is arbitrarily defined that is constrained by such reference projection. The method modifies the known structure of the fictitious object by comparing and optimizing its four projections to those of the unknown structure of the real object and continues to iterate until the optimization is limited by the residual sum of background noise. The method is composed of several sub-processes that acquire four projections from the real data and the fictitious object: generate an arbitrary distribution to define the fictitious object, optimize the four projections, generate a new distribution for the fictitious object, and enhance the reconstructed image. The sub-process for the acquisition of the four projections from the input real data is simply the function of acquiring the four projections from the data of the transmitted intensity. The transmitted intensity represents the density distribution, that is, the distribution of absorption coefficients through the object. 5 figs.

  7. Public Involvement and Communications Committee Page 1

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    June 1, 2011 FINAL MEETING SUMMARY HANFORD ADVISORY BOARD PUBLIC INVOLVEMENT & COMMUNICATIONS COMMITTEE MEETING June 1, 2011 Kennewick, WA Topics in this Meeting Summary Welcome and Introductions .......................................................................................................................... 1 Comprehensive Debrief - State of the Site Meetings ................................................................................... 4 Public Meetings - PW-1/3/6 and CW-5

  8. Simultaneous impact of neutron irradiation and sputtering on the surface structure of selfdamaged ITERgrade tungsten

    SciTech Connect (OSTI)

    Belyaeva, A. I. Savchenko, A. A.; Galuza, A. A.; Kolenov, I. V.

    2014-07-15

    Simultaneous effects of neutron irradiation and longterm sputtering on the surface relief of ITERgrade tungsten were studied. The effects of neutroninduced displacement damage have been simulated by irradiation of tungsten target with W{sup 6+} ions of 20?MeV energy. Ar{sup +} ions with energy 600?eV were used as imitation of charge exchange atoms in ITER. The surface relief was studied after each sputtering act. The singularity in the WJIG surface relief was ascertained experimentally at the first time, which determines the law of roughness extension under sputtering. As follows from the experimental data, the neutron irradiation has not to make a decisive additional contribution in the processes developing under impact of charge exchange atoms only.

  9. Resources for global risk assessment: The International Toxicity Estimates for Risk (ITER) and Risk Information Exchange (RiskIE) databases

    SciTech Connect (OSTI)

    Wullenweber, Andrea Kroner, Oliver; Kohrman, Melissa; Maier, Andrew; Dourson, Michael; Rak, Andrew; Wexler, Philip; Tomljanovic, Chuck

    2008-11-15

    The rate of chemical synthesis and use has outpaced the development of risk values and the resolution of risk assessment methodology questions. In addition, available risk values derived by different organizations may vary due to scientific judgments, mission of the organization, or use of more recently published data. Further, each organization derives values for a unique chemical list so it can be challenging to locate data on a given chemical. Two Internet resources are available to address these issues. First, the International Toxicity Estimates for Risk (ITER) database ( (www.tera.org/iter)) provides chronic human health risk assessment data from a variety of organizations worldwide in a side-by-side format, explains differences in risk values derived by different organizations, and links directly to each organization's website for more detailed information. It is also the only database that includes risk information from independent parties whose risk values have undergone independent peer review. Second, the Risk Information Exchange (RiskIE) is a database of in progress chemical risk assessment work, and includes non-chemical information related to human health risk assessment, such as training modules, white papers and risk documents. RiskIE is available at (http://www.allianceforrisk.org/RiskIE.htm), and will join ITER on National Library of Medicine's TOXNET ( (http://toxnet.nlm.nih.gov/)). Together, ITER and RiskIE provide risk assessors essential tools for easily identifying and comparing available risk data, for sharing in progress assessments, and for enhancing interaction among risk assessment groups to decrease duplication of effort and to harmonize risk assessment procedures across organizations.

  10. Sandia National Laboratories: Community Involvement: Volunteer Programs

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Community Involvement Contribution Programs Volunteer Programs Education Programs About Volunteer Programs Helping where we are needed Habitat for Humanity Employees and retirees are passionate about volunteering. You'll find Sandians judging science fairs, coaching sports teams, leading scouting troops, sorting food, building houses, and serving on community boards. In support of individual volunteer efforts, Sandia provides a volunteer website to advertise current volunteer opportunities and

  11. Sandia National Laboratories: About Sandia: Community Involvement:

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Education Programs: Science, Technology, Engineering and Math Programs Science, Technology, Engineering, and Math Programs Future scientists photo Our science, technology, engineering, and math (STEM) programs engage students by linking science to the real world. We offer three unique programs for American Indian students, African American students, and Hispanic students. The programs get students involved in fun, hands-on science and engineering activities and provide an opportunity to

  12. WE-G-18A-03: Cone Artifacts Correction in Iterative Cone Beam CT Reconstruction

    SciTech Connect (OSTI)

    Yan, H; Folkerts, M; Jiang, S; Jia, X; Wang, X; Bai, T; Lu, W

    2014-06-15

    Purpose: For iterative reconstruction (IR) in cone-beam CT (CBCT) imaging, data truncation along the superior-inferior (SI) direction causes severe cone artifacts in the reconstructed CBCT volume images. Not only does it reduce the effective SI coverage of the reconstructed volume, it also hinders the IR algorithm convergence. This is particular a problem for regularization based IR, where smoothing type regularization operations tend to propagate the artifacts to a large area. It is our purpose to develop a practical cone artifacts correction solution. Methods: We found it is the missing data residing in the truncated cone area that leads to inconsistency between the calculated forward projections and measured projections. We overcome this problem by using FDK type reconstruction to estimate the missing data and design weighting factors to compensate the inconsistency caused by the missing data. We validate the proposed methods in our multi-GPU low-dose CBCT reconstruction system on multiple patients' datasets. Results: Compared to the FDK reconstruction with full datasets, while IR is able to reconstruct CBCT images using a subset of projection data, the severe cone artifacts degrade overall image quality. For head-neck case under a full-fan mode, 13 out of 80 slices are contaminated. It is even more severe in pelvis case under half-fan mode, where 36 out of 80 slices are affected, leading to inferior soft-tissue delineation. By applying the proposed method, the cone artifacts are effectively corrected, with a mean intensity difference decreased from ∼497 HU to ∼39HU for those contaminated slices. Conclusion: A practical and effective solution for cone artifacts correction is proposed and validated in CBCT IR algorithm. This study is supported in part by NIH (1R01CA154747-01)

  13. Thermo-structural development of the ITER ICRF strap housing module

    SciTech Connect (OSTI)

    Winkler, K.; Shannon, M.; Lockley, D.

    2014-02-12

    Since March 2010 the preliminary design of the ITER ICRF Antennas have been developed by CYCLE, a consortium consisting of IPP (Garching), CCFE (Culham), CEA (Cadarache), Politecnico di Torino (Torino) and LPPERM/KMS (Brussels). This paper describes the steps taken to develop the present geometry of the triplet pair Strap Housing Module from a thermal and structural perspective, and shows the critical areas of the structure. Key issues are the manufacturability, (achieved by HIPing - Hot Isostatic Pressing), the ability to handle the radiating plasma thermal flux of 0.35 MW/m{sup 2}, the RF losses and the neutronic radiation. HIPing is necessary to achieve the complicated system of cooling channels inside the structure, which divides the coolant equally in order to supply each strap in the triplet with 1 l/s of water. The components have also to withstand the strong mechanical forces generated by plasma disruptions affecting all internal structures and the elevated design cooling water pressure of 5MPa. In order to maximise reliability, joints between different materials in the cooling water system have been kept to a minimum. Therefore, in the interests of fabricability and availability, the whole structure is manufactured out of stainless steel (316L(N)IG). The low conductivity of 316L(N)IG demands small wall thicknesses to avoid hot spots; however this reduces the mechanical strength. Consequently an in depth FEM analysis is presented, which was used to find and to improve the critical aspects of this important component and was the best means of finding the optimum between thermal and mechanical performance.

  14. Powerloads on the front end components and the duct of the heating and diagnostic neutral beam lines at ITER

    SciTech Connect (OSTI)

    Singh, M. J.; Boilson, D.; Hemsworth, R. S.; Geli, F.; Graceffa, J.; Urbani, M.; Schunke, B.; Chareyre, J.; Dlougach, E.; Krylov, A.

    2015-04-08

    The heating and current drive beam lines (HNB) at ITER are expected to deliver ∼16.7 MW power per beam line for H beams at 870 keV and D beams at 1 MeV during the H-He and the DD/DT phases of ITER operation respectively. On the other hand the diagnostic neutral beam (DNB) line shall deliver ∼2 MW power for H beams at 100 keV during both the phases. The path lengths over which the beams from the HNB and DNB beam lines need to be transported are 25.6 m and 20.7 m respectively. The transport of the beams over these path lengths results in beam losses, mainly by the direct interception of the beam with the beam line components and reionisation. The lost power is deposited on the surfaces of the various components of the beam line. In order to ensure the survival of these components over the operational life time of ITER, it is important to determine to the best possible extent the operational power loads and power densities on the various surfaces which are impacted by the beam in one way or the other during its transport. The main factors contributing to these are the divergence of the beamlets and the halo fraction in the beam, the beam aiming, the horizontal and vertical misalignment of the beam, and the gas profile along the beam path, which determines the re-ionisation loss, and the re-ionisation cross sections. The estimations have been made using a combination of the modified version of the Monte Carlo Gas Flow code (MCGF) and the BTR code. The MCGF is used to determine the gas profile in the beam line and takes into account the active gas feed into the ion source and neutraliser, the HNB-DNB cross over, the gas entering the beamline from the ITER machine, the additional gas atoms generated in the beam line due to impacting ions and the pumping speed of the cryopumps. The BTR code has been used to obtain the power loads and the power densities on the various surfaces of the front end components and the duct modules for different scenarios of ITER operation. The gas profile and the magnetic field distribution for each scenario has been considered in these evaluations. The worst case power loads and power densities for each surface have been used to study their thermo-mechanical behaviour and manufacturing feasibility. The details of these calculations and results obtained are presented and discussed.

  15. Evaluation of inter-laminar shear strength of GFRP composed of bonded glass/polyimide tapes and cyanate-ester/epoxy blended resin for ITER TF coils

    SciTech Connect (OSTI)

    Hemmi, T.; Matsui, K.; Koizumi, N. [Japan Atomic Energy Agency, Fusion Research and Development Directorate 801-1 Mukoyama, Naka, Ibaraki, 311-0193 (Japan); Nishimura, A. [National Institute for Fusion Science, Fusion Engineering Research Center 322-6 Oroshi-cho, Toki, Gifu, 509-5292 (Japan); Nishijima, S. [Osaka University, Division of Sustainable Energy and Environmental Engineering 1-1 Yamadaoka, Suita, Osaka, 565-0871 (Japan); Shikama, T. [Tohoku University, Institute for Materials Research 2-1-1 Katahira, Aoba, Sendai, Miyagi, 980-8577 (Japan)

    2014-01-27

    The insulation system of the ITER TF coils consists of multi-layer glass/polyimide tapes impregnated a cyanate-ester/epoxy resin. The ITER TF coils are required to withstand an irradiation of 10 MGy from gamma-ray and neutrons since the ITER TF coils is exposed by fast neutron (>0.1 MeV) of 10{sup 22} n/m{sup 2} during the ITER operation. Cyanate-ester/epoxy blended resins and bonded glass/polyimide tapes are developed as insulation materials to realize the required radiation-hardness for the insulation of the ITER TF coils. To evaluate the radiation-hardness of the developed insulation materials, the inter-laminar shear strength (ILSS) of glass-fiber reinforced plastics (GFRP) fabricated using developed insulation materials is measured as one of most important mechanical properties before/after the irradiation in a fission reactor of JRR-3M. As a result, it is demonstrated that the GFRPs using the developed insulation materials have a sufficient performance to apply for the ITER TF coil insulation.

  16. IDC Re-Engineering Phase 2 Iteration E1 Use Cases.

    SciTech Connect (OSTI)

    Harris, James M.; Carr, Dorthe B.; Coram, Jamie L.

    2016-01-01

    This document contains 21 use cases generated from the model contained in Rational Software Architect.

  17. Characterization of a constrained paired-view technique in iterative reconstruction for breast tomosynthesis

    SciTech Connect (OSTI)

    Wu, Gang; Yaffe, Martin J.; Mainprize, James G.

    2013-10-15

    Purpose: The order in which the projection views are employed in the reconstruction of tomosynthesis by iterative algorithms, such as simultaneous algebraic reconstruction technique and maximum likelihood, has a strong effect on the rate of convergence, accuracy, and the edge-blurring artifacts in the reconstructed image. The purpose of this investigation was to characterize and evaluate the effects of ordering schemes on image quality for breast tomosynthesis reconstruction and to explore a new constrained paired-view technique that could provide reduction of reconstruction artifacts. In this work, the authors compared several different ordering schemes and characterized the image quality and the formation of out-of-plane artifacts. Furthermore, a new normalization method is presented. It produces more accurate reconstructions with reduced artifacts comparing to the standard method of sequential ordering.Methods: In addition to visual assessment of image quality, several indices such as the signal-difference-to-noise ratio, the artifact-spread function, and the lesion detectability (d{sup ?}) were computed to quantitatively evaluate the effect of ordering scheme. The sets of breast tomosynthesis projection images were simulated for reconstruction; one set had uniform background (white noise only) and the other two contained both anatomic background and quantum noise. Clinical breast images were also studied for comparison.Results: The authors have quantified the image quality in reconstructed slices for a range of tumor sizes. The authors proposed method provides better performance for all of the metrics tested (contrast, d{sup ?}, and the level of artifacts) both for the uniform phantom case and in the presence of anatomical structure.Conclusions: The paired projection normalization provides better performance in the image quality of the reconstructed slices, and results in a lower level of artifacts in the Z direction. This implies that even a relatively simple method like the side-to-side sequence, which pairs two symmetrical projections with equal angular distance from the central projection, would achieve better reconstructed image quality than the conventional step-by-step method, which uses sequential projections one after another.

  18. SU-F-18C-06: Prospective Patient Evaluation of Iterative Reconstruction in Radiation Oncology

    SciTech Connect (OSTI)

    Price, R; Vance, S; Cattaneo, R; Schultz, L; Elshaikh, M; Chetty, I; Glide-Hurst, C

    2014-06-15

    Purpose: This work incorporates iterative reconstruction (IR) into a dose reduction study to characterize image quality metrics, delineation, and dosimetric assessment, with the goal of reducing imaging dose in Radiation Oncology. Methods: Three-dimensional noise power spectrum (NPS) analysis characterized noise magnitude/texture (120 kVp, 50200 mAs, IR levels 16 yielding noise reduction of 0.890.55 compared to filtered backprojection (FBP)). Task-specific Modulation Transfer Functions (MTFtask) were characterized across varied subject contrasts. A prospective dose reduction study (500 to 150 mAs) was conducted for 12 patients (43 inter-fraction CTs) for high-dose rate brachytherapy. Three physicians performed qualitative image assessment between full-dose FBP (FD-FBP, 500 mAs), low-dose FBP (LD-FBP, 150250 mAs), and low-dose IRL5-6 (LD-IR) scans for image noise, cuff/bladder interface detectability, spatial resolution, texture, and segmentation confidence. Comparisons between LD-FBP and LD-IR were conducted for the following metrics: delineation (bladder and rectum evaluated via overlap indices (OI) and Dice similarity coefficients (DSC)), noise, boundary changes, dose calculation, and digitally reconstructed radiographs (DRRs). Results: NPS showed ?50% reduction in noise magnitude and ?0.1 1/mm spatial frequency shift with IRL6. The largest MTFtask decrease between FBP and IR was 0.08 A.U. Qualitative patient image evaluation revealed LD-IR was equivalent or slightly worse than FD-FBP, and superior to LD-FBP for all metrics except low contrast interface and texture. The largest CT number discrepancy from FBP occurred at a bone/tissue interface using IRL6 (?1.2 4.9 HU (range: ?17.6 12.5 HU)). No significant contour differences (OIs and DSCs = 0.85 0.95) and dose calculation discrepancy (<0.02%) were observed. DRRs preserved anatomical detail and demonstrated <2% difference in intensity between LD-FBP and LD-IRL6. Conclusion: While phantom analysis showed slight noise texture differences with IR, patient results revealed that image quality, contouring ability, and dosimetric parameters were not adversely affected, thus support integrating IR into treatment planning. Research supported in part by a grant from Philips HealthCare.

  19. Failure analysis of beryllium tile assembles following high heat flux testing for the ITER program

    SciTech Connect (OSTI)

    B. C. Odegard, Jr.; C. H. Cadden; N. Y. C. Yang

    2000-05-01

    The following document describes the processing, testing and post-test analysis of two Be-Cu assemblies that have successfully met the heat load requirements for the first wall and dome sections for the ITER (International Thermonuclear Experimental Reactor) fusion reactor. Several different joint assemblies were evaluated in support of a manufacturing technology investigation aimed at diffusion bonding or brazing a beryllium armor tile to a copper alloy heat sink for fusion reactor applications. Judicious selection of materials and coatings for these assemblies was essential to eliminate or minimize interactions with the highly reactive beryllium armor material. A thin titanium layer was used as a diffusion barrier to isolate the copper heat sink from the beryllium armor. To reduce residual stresses produced by differences in the expansion coefficients between the beryllium and copper, a compliant layer of aluminum or aluminum-beryllium (AlBeMet-150) was used. Aluminum was chosen because it does not chemically react with, and exhibits limited volubility in, beryllium. Two bonding processes were used to produce the assemblies. The primary process was a diffusion bonding technique. In this case, undesirable metallurgical reactions were minimized by keeping the materials in a solid state throughout the fabrication cycle. The other process employed an aluminum-silicon layer as a brazing filler material. In both cases, a hot isostatic press (HIP) furnace was used in conjunction with vacuum-canned assemblies in order to minimize oxidation and provide sufficient pressure on the assemblies for full metal-to-metal contact and subsequent bonding. The two final assemblies were subjected to a suite of tests including: tensile tests and electron and optical metallography. Finally, high heat flux testing was conducted at the electron beam testing system (EBTS) at Sandia National Laboratories, New Mexico. Here, test mockups were fabricated and subjected to normal heat loads to 10 MW/m{sup 2} (3 Hz) and abnormal heat loads to 250 MJ/m{sup 2} (0.5s) to determine their performance under simulated fusion reactor conditions for first wall components. Both assemblies survived the normal heat loads with no visual damage. Optical and electron microscopy were used to evaluate the extent of the damage at the interfaces following the VDE simulations.

  20. Apolipoprotein gene involved in lipid metabolism

    DOE Patents [OSTI]

    Rubin, Edward; Pennacchio, Len A.

    2007-07-03

    Methods and materials for studying the effects of a newly identified human gene, APOAV, and the corresponding mouse gene apoAV. The sequences of the genes are given, and transgenic animals which either contain the gene or have the endogenous gene knocked out are described. In addition, single nucleotide polymorphisms (SNPs) in the gene are described and characterized. It is demonstrated that certain SNPs are associated with diseases involving lipids and triglycerides and other metabolic diseases. These SNPs may be used alone or with SNPs from other genes to study individual risk factors. Methods for intervention in lipid diseases, including the screening of drugs to treat lipid-related or diabetic diseases are also disclosed.

  1. Combined iterative reconstruction and image-domain decomposition for dual energy CT using total-variation regularization

    SciTech Connect (OSTI)

    Dong, Xue; Niu, Tianye; Zhu, Lei

    2014-05-15

    Purpose: Dual-energy CT (DECT) is being increasingly used for its capability of material decomposition and energy-selective imaging. A generic problem of DECT, however, is that the decomposition process is unstable in the sense that the relative magnitude of decomposed signals is reduced due to signal cancellation while the image noise is accumulating from the two CT images of independent scans. Direct image decomposition, therefore, leads to severe degradation of signal-to-noise ratio on the resultant images. Existing noise suppression techniques are typically implemented in DECT with the procedures of reconstruction and decomposition performed independently, which do not explore the statistical properties of decomposed images during the reconstruction for noise reduction. In this work, the authors propose an iterative approach that combines the reconstruction and the signal decomposition procedures to minimize the DECT image noise without noticeable loss of resolution. Methods: The proposed algorithm is formulated as an optimization problem, which balances the data fidelity and total variation of decomposed images in one framework, and the decomposition step is carried out iteratively together with reconstruction. The noise in the CT images from the proposed algorithm becomes well correlated even though the noise of the raw projections is independent on the two CT scans. Due to this feature, the proposed algorithm avoids noise accumulation during the decomposition process. The authors evaluate the method performance on noise suppression and spatial resolution using phantom studies and compare the algorithm with conventional denoising approaches as well as combined iterative reconstruction methods with different forms of regularization. Results: On the Catphan600 phantom, the proposed method outperforms the existing denoising methods on preserving spatial resolution at the same level of noise suppression, i.e., a reduction of noise standard deviation by one order of magnitude. This improvement is mainly attributed to the high noise correlation in the CT images reconstructed by the proposed algorithm. Iterative reconstruction using different regularization, including quadratic orq-generalized Gaussian Markov random field regularization, achieves similar noise suppression from high noise correlation. However, the proposed TV regularization obtains a better edge preserving performance. Studies of electron density measurement also show that our method reduces the average estimation error from 9.5% to 7.1%. On the anthropomorphic head phantom, the proposed method suppresses the noise standard deviation of the decomposed images by a factor of ?14 without blurring the fine structures in the sinus area. Conclusions: The authors propose a practical method for DECT imaging reconstruction, which combines the image reconstruction and material decomposition into one optimization framework. Compared to the existing approaches, our method achieves a superior performance on DECT imaging with respect to decomposition accuracy, noise reduction, and spatial resolution.

  2. IDC Use Case Model Survey Version 1.1.

    SciTech Connect (OSTI)

    Harris, James Mark; Carr, Dorthe B.

    2015-02-01

    This document contains the brief descriptions for the actors and use cases contained in the IDC Use Case Model. REVISIONS Version Date Author/Team Revision Description Authorized by V1.0 12/2014 SNL IDC Reengineering Project Team Initial delivery M. Harris V1.1 2/2015 SNL IDC Reengineering Project Team Iteration I2 Review Comments M. Harris

  3. Genomic Aspects of Research Involving Polyploid Plants

    SciTech Connect (OSTI)

    Yang, Xiaohan [ORNL; Ye, Chuyu [ORNL; Tschaplinski, Timothy J [ORNL; Wullschleger, Stan D [ORNL; Tuskan, Gerald A [ORNL

    2011-01-01

    Almost all extant plant species have spontaneously doubled their genomes at least once in their evolutionary histories, resulting in polyploidy which provided a rich genomic resource for evolutionary processes. Moreover, superior polyploid clones have been created during the process of crop domestication. Polyploid plants generated by evolutionary processes and/or crop domestication have been the intentional or serendipitous focus of research dealing with the dynamics and consequences of genome evolution. One of the new trends in genomics research is to create synthetic polyploid plants which provide materials for studying the initial genomic changes/responses immediately after polyploid formation. Polyploid plants are also used in functional genomics research to study gene expression in a complex genomic background. In this review, we summarize the recent progress in genomics research involving ancient, young, and synthetic polyploid plants, with a focus on genome size evolution, genomics diversity, genomic rearrangement, genetic and epigenetic changes in duplicated genes, gene discovery, and comparative genomics. Implications on plant sciences including evolution, functional genomics, and plant breeding are presented. It is anticipated that polyploids will be a regular subject of genomics research in the foreseeable future as the rapid advances in DNA sequencing technology create unprecedented opportunities for discovering and monitoring genomic and transcriptomic changes in polyploid plants. The fast accumulation of knowledge on polyploid formation, maintenance, and divergence at whole-genome and subgenome levels will not only help plant biologists understand how plants have evolved and diversified, but also assist plant breeders in designing new strategies for crop improvement.

  4. Clinical evaluation of the iterative metal artifact reduction algorithm for CT simulation in radiotherapy

    SciTech Connect (OSTI)

    Axente, Marian; Von Eyben, Rie; Hristov, Dimitre; Paidi, Ajay; Bani-Hashemi, Ali; Zeng, Chuan; Krauss, Andreas

    2015-03-15

    Purpose: To clinically evaluate an iterative metal artifact reduction (IMAR) algorithm prototype in the radiation oncology clinic setting by testing for accuracy in CT number retrieval, relative dosimetric changes in regions affected by artifacts, and improvements in anatomical and shape conspicuity of corrected images. Methods: A phantom with known material inserts was scanned in the presence/absence of metal with different configurations of placement and sizes. The relative change in CT numbers from the reference data (CT with no metal) was analyzed. The CT studies were also used for dosimetric tests where dose distributions from both photon and proton beams were calculated. Dose differences and gamma analysis were calculated to quantify the relative changes between doses calculated on the different CT studies. Data from eight patients (all different treatment sites) were also used to quantify the differences between dose distributions before and after correction with IMAR, with no reference standard. A ranking experiment was also conducted to analyze the relative confidence of physicians delineating anatomy in the near vicinity of the metal implants. Results: IMAR corrected images proved to accurately retrieve CT numbers in the phantom study, independent of metal insert configuration, size of the metal, and acquisition energy. For plastic water, the mean difference between corrected images and reference images was −1.3 HU across all scenarios (N = 37) with a 90% confidence interval of [−2.4, −0.2] HU. While deviations were relatively higher in images with more metal content, IMAR was able to effectively correct the CT numbers independent of the quantity of metal. Residual errors in the CT numbers as well as some induced by the correction algorithm were found in the IMAR corrected images. However, the dose distributions calculated on IMAR corrected images were closer to the reference data in phantom studies. Relative spatial difference in the dose distributions in the regions affected by the metal artifacts was also observed in patient data. However, in absence of a reference ground truth (CT set without metal inserts), these differences should not be interpreted as improvement/deterioration of the accuracy of calculated dose. With limited data presented, it was observed that proton dosimetry was affected more than photons as expected. Physicians were significantly more confident contouring anatomy in the regions affected by artifacts. While site specific preferences were detected, all indicated that they would consistently use IMAR corrected images. Conclusions: IMAR correction algorithm could be readily implemented in an existing clinical workflow upon commercial release. While residual errors still exist in IMAR corrected images, these images present with better overall conspicuity of the patient/phantom geometry and offer more accurate CT numbers for improved local dosimetry. The variety of different scenarios included herein attest to the utility of the evaluated IMAR for a wide range of radiotherapy clinical scenarios.

  5. Long pulse acceleration of MeV class high power density negative H{sup −} ion beam for ITER

    SciTech Connect (OSTI)

    Umeda, N. Kojima, A.; Kashiwagi, M.; Tobari, H.; Hiratsuka, J.; Watanabe, K.; Dairaku, M.; Yamanaka, H.; Hanada, M.

    2015-04-08

    R and D of high power density negative ion beam acceleration has been carried out at MeV test facility in JAEA to realize ITER neutral beam accelerator. The main target is H{sup −} ion beam acceleration up to 1 MeV with 200 A/m{sup 2} for 60 s whose pulse length is the present facility limit. For long pulse acceleration at high power density, new extraction grid (EXG) has been developed with high cooling capability, which electron suppression magnet is placed under cooling channel similar to ITER. In addition, aperture size of electron suppression grid (ESG) is enlarged from 14 mm to 16 mm to reduce direct interception on the ESG and emission of secondary electron which leads to high heat load on the upstream acceleration grid. By enlarging ESG aperture, beam current increased 10 % at high current beam and total acceleration grid heat load reduced from 13 % to 10 % of input power at long pulse beam. In addition, heat load by back stream positive ion into the EXG is measured for the first time and is estimated as 0.3 % of beam power, while heat load by back stream ion into the source chamber is estimated as 3.5 ~ 4.0 % of beam power. Beam acceleration up to 60 s which is the facility limit, has achieved at 683 keV, 100 A/m{sup 2} of negative ion beam, whose energy density increases two orders of magnitude since 2011.

  6. Development of a laser cleaning method for the first mirror surface of the charge exchange recombination spectroscopy diagnostics on ITER

    SciTech Connect (OSTI)

    Kuznetsov, A. P.; Buzinskij, O. I.; Gubsky, K. L.; Nikitina, E. A.; Savchenkov, A. V.; Tarasov, B. A.; Tugarinov, S. N.

    2015-12-15

    A set of optical diagnostics is expected for measuring the plasma characteristics in ITER. Optical elements located inside discharge chambers are exposed to an intense radiation load, sputtering due to collisions with energetic atoms formed in the charge transfer processes, and contamination due to recondensation of materials sputtered from different parts of the construction of the chamber. Removing the films of the sputtered materials from the mirrors with the aid of pulsed laser radiation is an efficient cleaning method enabling recovery of the optical properties of the mirrors. In this work, we studied the efficiency of removal of metal oxide films by pulsed radiation of a fiber laser. Optimization of the laser cleaning conditions was carried out on samples representing metal substrates polished with optical quality with deposition of films on them imitating the chemical composition and conditions expected in ITER. It is shown that, by a proper selection of modes of radiation exposure to the surface with a deposited film, it is feasible to restore the original high reflection characteristics of optical elements.

  7. Enhanced Confinement Scenarios Without Large Edge Localized Modes in Tokamaks: Control, Performance, and Extrapolability Issues for ITER

    SciTech Connect (OSTI)

    Maingi, R

    2014-07-01

    Large edge localized modes (ELMs) typically accompany good H-mode confinement in fusion devices, but can present problems for plasma facing components because of high transient heat loads. Here the range of techniques for ELM control deployed in fusion devices is reviewed. The two baseline strategies in the ITER baseline design are emphasized: rapid ELM triggering and peak heat flux control via pellet injection, and the use of magnetic perturbations to suppress or mitigate ELMs. While both of these techniques are moderately well developed, with reasonable physical bases for projecting to ITER, differing observations between multiple devices are also discussed to highlight the needed community R & D. In addition, recent progress in ELM-free regimes, namely Quiescent H-mode, I-mode, and Enhanced Pedestal H-mode is reviewed, and open questions for extrapolability are discussed. Finally progress and outstanding issues in alternate ELM control techniques are reviewed: supersonic molecular beam injection, edge electron cyclotron heating, lower hybrid heating and/or current drive, controlled periodic jogs of the vertical centroid position, ELM pace-making via periodic magnetic perturbations, ELM elimination with lithium wall conditioning, and naturally occurring small ELM regimes.

  8. A collisional radiative model for caesium and its application to an RF source for negative hydrogen ions

    SciTech Connect (OSTI)

    Wnderlich, D. Wimmer, C.; Friedl, R.

    2015-04-08

    A collisional radiative (CR) model for caesium atoms in low-temperature, low-pressure hydrogen-caesium plasmas is introduced. This model includes the caesium ground state, 14 excited states, the singly charged caesium ion and the negative hydrogen ion. The reaction probabilities needed as input are based on data from the literature, using some scaling and extrapolations. Additionally, new cross sections for electron collision ionization and three-body recombination have been calculated. The relevance of mutual neutralization of positive caesium ions and negative hydrogen ions is highlighted: depending on the densities of the involved particle species, this excitation channel can have a significant influence on the population densities of excited states in the caesium atom. This strong influence is successfully verified by optical emission spectroscopy measurements performed at the IPP prototype negative hydrogen ion source for ITER NBI. As a consequence, population models for caesium in electronegative low-temperature, low-pressure hydrogen-caesium plasmas need to take into account the mutual neutralization process. The present CR model is an example for such models and represents an important prerequisite for deducing the total caesium density in surface production based negative hydrogen ion sources.

  9. Surface interactions involved in flashover with high density electronegative gases.

    SciTech Connect (OSTI)

    Hodge, Keith Conquest; Warne, Larry Kevin; Jorgenson, Roy Eberhardt; Wallace, Zachariah Red; Lehr, Jane Marie

    2010-01-01

    This report examines the interactions involved with flashover along a surface in high density electronegative gases. The focus is on fast ionization processes rather than the later time ionic drift or thermalization of the discharge. A kinetic simulation of the gas and surface is used to examine electron multiplication and includes gas collision, excitation and ionization, and attachment processes, gas photoionization and surface photoemission processes, as well as surface attachment. These rates are then used in a 1.5D fluid ionization wave (streamer) model to study streamer propagation with and without the surface in air and in SF6. The 1.5D model therefore includes rates for all these processes. To get a better estimate for the behavior of the radius we have studied radial expansion of the streamer in air and in SF6. The focus of the modeling is on voltage and field level changes (with and without a surface) rather than secondary effects, such as, velocities or changes in discharge path. An experiment has been set up to carry out measurements of threshold voltages, streamer velocities, and other discharge characteristics. This setup includes both electrical and photographic diagnostics (streak and framing cameras). We have observed little change in critical field levels (where avalanche multiplication sets in) in the gas alone versus with the surface. Comparisons between model calculations and experimental measurements are in agreement with this. We have examined streamer sustaining fields (field which maintains ionization wave propagation) in the gas and on the surface. Agreement of the gas levels with available literature is good and agreement between experiment and calculation is good also. Model calculations do not indicate much difference between the gas alone versus the surface levels. Experiments have identified differences in velocity between streamers on the surface and in the gas alone (the surface values being larger).

  10. Near-field/altered-zone models report

    SciTech Connect (OSTI)

    Hardin, E. L., LLNL

    1998-03-01

    The U.S. Department of Energy is studying Yucca Mountain as the possible site for the first underground repository for permanent disposal of spent fuel from commercial nuclear reactors as well as for other types high-level nuclear waste. Emplacement of high-level radioactive waste, especially commercial spent nuclear fuel (CSNF), in Yucca Mountain will release a large amount of heat into the rock above and below the repository. The heating rate will decrease with time, creating a thermal pulse. Over a period of several thousand years, the rock temperature will rise initially, then drop when the production of decay heat falls below the rate at which heat escapes from the hot zone. Besides raising the rock temperature, much of this heat will vaporize water, which will then condense in cooler regions. The condensate is likely to form a gravity-driven heat pipe above the repository, creating the possibility that water may drain back onto the waste packages (WPs) or that it may ''shed'' through the pillars between emplacement drifts. The long-term importance of these effects has been investigated through the development, testing, and application of thermohydrologic (TH) models. Other effects, such coupled chemical and mechanical processes, may also influence the movement of water above, within, and below the emplacement drifts. A recent report on thermally driven coupled processes (Hardin and Chesnut, 1997) provides a qualitative assessment of the probable significance of these processes for the Yucca Mountain Site Characterization Project (YMSCP) and is the phenomenological framework for the present report. This report describes the conceptual and numerical models that have been developed to predict the thermal, mechanical, hydrologic, and chemical responses to the cumulative heat production of the potential host rock at Yucca Mountain. As proposed, the repository horizon will be situated within the Topopah Spring tuff, in the adjacent middle nonlithophysal and lower lithophysal units. These units are made up of moderately to densely welded, devitrified, fractured tuff. The rock's chemical composition is comparable to that of typical granite, but has textural features and mineralogical characteristics of large-scale, silicic volcanism. Because the repository horizon will be approximately 300 m below the ground surface and 200 m above the water table, the repository will be partially saturated. The welded tuff matrix in the host units is highly impermeable, but water and gas flow readily through fractures. The degree of fracturing in these units is highly variable, and the hydrologic significance of fracturing is an important aspect of site investigation. This report describes the characterization and modeling of a region around the potential repository--the altered zone--a region in which the temperature will be increased significantly by waste-generated heat. Numerical simulation has shown that, depending on the boundary conditions, rock properties, and repository design features incorporated in the models, the altered zone (AZ) may extend from the water table to the ground surface. This report also describes models of the near field, the region comprising the repository emplacement drifts and the surrounding rock, which are critical to the performance of engineered components. Investigations of near-field and altered-zone (NF/AZ) processes support the design of underground repository facilities and engineered barriers and also provide constraint data for probabilistic calculations of waste-isolation performance (i.e., performance assessment). The approach to investigation, which is an iterative process involving hypothesis testing and experimentation, has relied on conceptualizing engineered barriers and on performance analysis. This report is a collection, emphasizing conceptual and numerical models, of the recent results contributed from studies of NF/AZ processes and of quantitative measures of NF/AZ performance. The selection and presentation of contributions are intended to show the iterative development of understand

  11. Phase retrieval with the transport-of-intensity equation in an arbitrarily-shaped aperture by iterative discrete cosine transforms

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Huang, Lei; Zuo, Chao; Idir, Mourad; Qu, Weijuan; Asundi, Anand

    2015-04-21

    A novel transport-of-intensity equation (TIE) based phase retrieval method is proposed with putting an arbitrarily-shaped aperture into the optical wavefield. In this arbitrarily-shaped aperture, the TIE can be solved under non-uniform illuminations and even non-homogeneous boundary conditions by iterative discrete cosine transforms with a phase compensation mechanism. Simulation with arbitrary phase, arbitrary aperture shape, and non-uniform intensity distribution verifies the effective compensation and high accuracy of the proposed method. Experiment is also carried out to check the feasibility of the proposed method in real measurement. Comparing to the existing methods, the proposed method is applicable for any types of phasemore » distribution under non-uniform illumination and non-homogeneous boundary conditions within an arbitrarily-shaped aperture, which enables the technique of TIE with hard aperture become a more flexible phase retrieval tool in practical measurements.« less

  12. 10.0 COMMUNITY RELATIONS/PUBLIC INVOLVEMENT

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    0-1 10.0 COMMUNITY RELATIONSPUBLIC INVOLVEMENT 10.1 INTRODUCTION This section describes, in general, the way in which the public will be involved with the implementation of this...

  13. System Advisor Model

    Energy Science and Technology Software Center (OSTI)

    2010-03-01

    The System Advisor Model (SAM) is a performance and economic model designed to facilitate decision making for people involved in the renewable energy industry, ranging from project managers and engineers to incentive program designers, technology developers, and researchers.

  14. UNSAT-H Version 3.0: Unsaturated Soil Water and Heat Flow Model Theory, User Manual, and Examples

    SciTech Connect (OSTI)

    MJ Fayer

    2000-06-12

    The UNSAT-H model was developed at Pacific Northwest National Laboratory (PNNL) to assess the water dynamics of arid sites and, in particular, estimate recharge fluxes for scenarios pertinent to waste disposal facilities. During the last 4 years, the UNSAT-H model received support from the Immobilized Waste Program (IWP) of the Hanford Site's River Protection Project. This program is designing and assessing the performance of on-site disposal facilities to receive radioactive wastes that are currently stored in single- and double-shell tanks at the Hanford Site (LMHC 1999). The IWP is interested in estimates of recharge rates for current conditions and long-term scenarios involving the vadose zone disposal of tank wastes. Simulation modeling with UNSAT-H is one of the methods being used to provide those estimates (e.g., Rockhold et al. 1995; Fayer et al. 1999). To achieve the above goals for assessing water dynamics and estimating recharge rates, the UNSAT-H model addresses soil water infiltration, redistribution, evaporation, plant transpiration, deep drainage, and soil heat flow as one-dimensional processes. The UNSAT-H model simulates liquid water flow using Richards' equation (Richards 1931), water vapor diffusion using Fick's law, and sensible heat flow using the Fourier equation. This report documents UNSAT-H .Version 3.0. The report includes the bases for the conceptual model and its numerical implementation, benchmark test cases, example simulations involving layered soils and plants, and the code manual. Version 3.0 is an, enhanced-capability update of UNSAT-H Version 2.0 (Fayer and Jones 1990). New features include hysteresis, an iterative solution of head and temperature, an energy balance check, the modified Picard solution technique, additional hydraulic functions, multiple-year simulation capability, and general enhancements.

  15. Workplace Charging Challenge Partner: JLA Public Involvement | Department

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    of Energy JLA Public Involvement Workplace Charging Challenge Partner: JLA Public Involvement Workplace Charging Challenge Partner: JLA Public Involvement Joined the Challenge: March 2013 Headquarters: Portland, OR Charging Location: Portland, OR Domestic Employees: 15 Purchasing a plug-in electric vehicle (PEV) and installing a charging station has expanded JLA Public Involvement's sustainability efforts and allowed them to achieve Gold certification in the City of Portland's Sustainability

  16. Fusion Materials Science and Technology Research Opportunities now and during the ITER Era

    SciTech Connect (OSTI)

    Zinkle, Steven J.; Blanchard, James; Callis, Richard W.; Kessel, Charles E.; Kurtz, Richard J.; Lee, Peter J.; Mccarthy, Kathryn; Morley, Neil; Najmabadi, Farrokh; Nygren, Richard; Tynan, George R.; Whyte, Dennis G.; Willms, Scott; Wirth, Brian D.

    2014-03-13

    Several high-priority near-term potential research activities to address fusion nuclear science challenges are summarized. General recommendations include: 1) Research should be preferentially focused on the most technologically advanced options (i.e., options that have been developed at least through the single-effects concept exploration stage, Technology Readiness Levels >3), 2) Significant near-term progress can be achieved by modifying existing facilities and/or moderate investment in new medium-scale facilities, and 3) Computational modeling for fusion nuclear sciences is generally not yet sufficiently robust to enable truly predictive results to be obtained, but large reductions in risk, cost and schedule can be achieved by careful integration of experiment and modeling.

  17. Fusion materials science and technology research opportunities now and during the ITER era

    SciTech Connect (OSTI)

    S.J. Zinkle; J.P. Planchard; R.W. Callis; C.E. Kessel; P.J. Lee; K.A. McCarty; Various Others

    2014-10-01

    Several high-priority near-term potential research activities to address fusion nuclear science challenges are summarized. General recommendations include: (1) Research should be preferentially focused on the most technologically advanced options (i.e., options that have been developed at least through the singleeffects concept exploration stage, technology readiness levels >3), (2) Significant near-term progress can be achieved by modifying existing facilities and/or moderate investment in new medium-scale facilities, and (3) Computational modeling for fusion nuclear sciences is generally not yet sufficiently robust to enable truly predictive results to be obtained, but large reductions in risk, cost and schedule can be achieved by careful integration of experiment and modeling.

  18. SU-E-I-93: Improved Imaging Quality for Multislice Helical CT Via Sparsity Regularized Iterative Image Reconstruction Method Based On Tensor Framelet

    SciTech Connect (OSTI)

    Nam, H; Guo, M; Lee, K; Li, R; Xing, L; Gao, H

    2014-06-01

    Purpose: Inspired by compressive sensing, sparsity regularized iterative reconstruction method has been extensively studied. However, its utility pertinent to multislice helical 4D CT for radiotherapy with respect to imaging quality, dose, and time has not been thoroughly addressed. As the beginning of such an investigation, this work carries out the initial comparison of reconstructed imaging quality between sparsity regularized iterative method and analytic method through static phantom studies using a state-of-art 128-channel multi-slice Siemens helical CT scanner. Methods: In our iterative method, tensor framelet (TF) is chosen as the regularization method for its superior performance from total variation regularization in terms of reduced piecewise-constant artifacts and improved imaging quality that has been demonstrated in our prior work. On the other hand, X-ray transforms and its adjoints are computed on-the-fly through GPU implementation using our previous developed fast parallel algorithms with O(1) complexity per computing thread. For comparison, both FDK (approximate analytic method) and Katsevich algorithm (exact analytic method) are used for multislice helical CT image reconstruction. Results: The phantom experimental data with different imaging doses were acquired using a state-of-art 128-channel multi-slice Siemens helical CT scanner. The reconstructed image quality was compared between TF-based iterative method, FDK and Katsevich algorithm with the quantitative analysis for characterizing signal-to-noise ratio, image contrast, and spatial resolution of high-contrast and low-contrast objects. Conclusion: The experimental results suggest that our tensor framelet regularized iterative reconstruction algorithm improves the helical CT imaging quality from FDK and Katsevich algorithm for static experimental phantom studies that have been performed.

  19. Prototype indicators of value added through public involvement

    SciTech Connect (OSTI)

    Lach, D.; Hixson, P.; Ramonas, L.

    1995-12-01

    As more managers realize that public input in public sector decision making is a given in the current political and social climate, many are turning to public involvement as a way to manage input so that it is beneficial to their decisions and projects. Public involvement is starting to become a familiar way of doing business for many Federal agencies and its contractors. Yet, many, if not most agency and contractor managers are still unclear about the value and costs that public involvement adds to their projects. Proponents claim that public involvement increases the acceptability of project goals by increasing stakeholders` knowledge about and involvement in decisions of importance to them. In spite of these assertions avowing the benefits of public involvement, proponents have not generated methods that demonstrate or provide evidence of such value added through incorporating public involvement into projects. As these questions about the value and costs of public involvement efforts increase, there is a pressing need to document the value and costs of public involvement for the participants in these processes--the stakeholders--and to present this information to decision makers in ways that help them assess the value and costs of managing public input through a public involvement program.

  20. The iterative thermal emission method: A more implicit modification of IMC

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Long, A. R.; Gentile, N. A.; Palmer, T. S.

    2014-08-19

    For over 40 years, the Implicit Monte Carlo (IMC) method has been used to solve challenging problems in thermal radiative transfer. These problems typically contain regions that are optically thick and diffusive, as a consequence of the high degree of “pseudo-scattering” introduced to model the absorption and reemission of photons from a tightly-coupled, radiating material. IMC has several well-known features that could be improved: a) it can be prohibitively computationally expensive, b) it introduces statistical noise into the material and radiation temperatures, which may be problematic in multiphysics simulations, and c) under certain conditions, solutions can be nonphysical, in thatmore » they violate a maximum principle, where IMC-calculated temperatures can be greater than the maximum temperature used to drive the problem.« less

  1. Technical Note: Measuring contrast- and noise-dependent spatial resolution of an iterative reconstruction method in CT using ensemble averaging

    SciTech Connect (OSTI)

    Yu, Lifeng Vrieze, Thomas J.; Leng, Shuai; Fletcher, Joel G.; McCollough, Cynthia H.

    2015-05-15

    Purpose: The spatial resolution of iterative reconstruction (IR) in computed tomography (CT) is contrast- and noise-dependent because of the nonlinear regularization. Due to the severe noise contamination, it is challenging to perform precise spatial-resolution measurements at very low-contrast levels. The purpose of this study was to measure the spatial resolution of a commercially available IR method using ensemble-averaged images acquired from repeated scans. Methods: A low-contrast phantom containing three rods (7, 14, and 21 HU below background) was scanned on a 128-slice CT scanner at three dose levels (CTDI{sub vol} = 16, 8, and 4 mGy). Images were reconstructed using two filtered-backprojection (FBP) kernels (B40 and B20) and a commercial IR method (sinogram affirmed iterative reconstruction, SAFIRE, Siemens Healthcare) with two strength settings (I40-3 and I40-5). The same scan was repeated 100 times at each dose level. The modulation transfer function (MTF) was calculated based on the edge profile measured on the ensemble-averaged images. Results: The spatial resolution of the two FBP kernels, B40 and B20, remained relatively constant across contrast and dose levels. However, the spatial resolution of the two IR kernels degraded relative to FBP as contrast or dose level decreased. For a given dose level at 16 mGy, the MTF{sub 50%} value normalized to the B40 kernel decreased from 98.4% at 21 HU to 88.5% at 7 HU for I40-3 and from 97.6% to 82.1% for I40-5. At 21 HU, the relative MTF{sub 50%} value decreased from 98.4% at 16 mGy to 90.7% at 4 mGy for I40-3 and from 97.6% to 85.6% for I40-5. Conclusions: A simple technique using ensemble averaging from repeated CT scans can be used to measure the spatial resolution of IR techniques in CT at very low contrast levels. The evaluated IR method degraded the spatial resolution at low contrast and high noise levels.

  2. Integrated Experimental and Model-based Analysis Reveals the Spatial Aspects of EGFR Activation Dynamics

    SciTech Connect (OSTI)

    Shankaran, Harish; Zhang, Yi; Chrisler, William B.; Ewald, Jonathan A.; Wiley, H. S.; Resat, Haluk

    2012-10-02

    The epidermal growth factor receptor (EGFR) belongs to the ErbB family of receptor tyrosine kinases, and controls a diverse set of cellular responses relevant to development and tumorigenesis. ErbB activation is a complex process involving receptor-ligand binding, receptor dimerization, phosphorylation, and trafficking (internalization, recycling and degradation), which together dictate the spatio-temporal distribution of active receptors within the cell. The ability to predict this distribution, and elucidation of the factors regulating it, would help to establish a mechanistic link between ErbB expression levels and the cellular response. Towards this end, we constructed mathematical models for deconvolving the contributions of receptor dimerization and phosphorylation to EGFR activation, and to examine the dependence of these processes on sub-cellular location. We collected experimental datasets for EGFR activation dynamics in human mammary epithelial cells, with the specific goal of model parameterization, and used the data to estimate parameters for several alternate models. Model-based analysis indicated that: 1) signal termination via receptor dephosphorylation in late endosomes, prior to degradation, is an important component of the response, 2) less than 40% of the receptors in the cell are phosphorylated at any given time, even at saturating ligand doses, and 3) receptor dephosphorylation rates at the cell surface and early endosomes are comparable. We validated the last finding by measuring EGFR dephosphorylation rates at various times following ligand addition both in whole cells, and in endosomes using ELISAs and fluorescent imaging. Overall, our results provide important information on how EGFR phosphorylation levels are regulated within cells. Further, the mathematical model described here can be extended to determine receptor dimer abundances in cells co-expressing various levels of ErbB receptors. This study demonstrates that an iterative cycle of experiments and modeling can be used to gain mechanistic insight regarding complex cell signaling networks.

  3. Sequentially Executed Model Evaluation Framework

    Energy Science and Technology Software Center (OSTI)

    2014-02-14

    Provides a message passing framework between generic input, model and output drivers, and specifies an API for developing such drivers. Also provides batch and real-time controllers which step the model and 1/0 through the time domain (or other discrete domain), and sample 1/0 drivers. This is a Framework library framework, and does not, itself, solve any problems or execute any modelling. The SeMe framework aids in development of models which operate on sequential information, suchmore » as time-series, where evaluation is based on prior results combined with new data for this iteration. Ha) applications in quality monitoring, and was developed as part of the CANARY-EDS software, where real-time water quality data is being analyzed« less

  4. Sequentially Executed Model Evaluation Framework

    SciTech Connect (OSTI)

    2014-02-14

    Provides a message passing framework between generic input, model and output drivers, and specifies an API for developing such drivers. Also provides batch and real-time controllers which step the model and 1/0 through the time domain (or other discrete domain), and sample 1/0 drivers. This is a Framework library framework, and does not, itself, solve any problems or execute any modelling. The SeMe framework aids in development of models which operate on sequential information, such as time-series, where evaluation is based on prior results combined with new data for this iteration. Ha) applications in quality monitoring, and was developed as part of the CANARY-EDS software, where real-time water quality data is being analyzed

  5. DOE Involvement in Consensus Negotiations for Energy Conservation Standards

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    | Department of Energy Involvement in Consensus Negotiations for Energy Conservation Standards DOE Involvement in Consensus Negotiations for Energy Conservation Standards DOE Involvement in Consensus Negotiations for Energy Conservation Standards. The Department of Energy is supportive of outside parties' negotiations efforts to reach consensus on energy conservation standards and test procedures that can be presented for consideration by the Department However, neither the Department nor

  6. Draft Public Involvement Advice for Central Plateau Cleanup

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    V0, 12914 Draft Public Involvement Advice for Central Plateau Cleanup Principles Issue managers: Pollet, Mattson, Vanni, Plahuta, Catrell Background The Tri-Party Agencies are...

  7. Tri-Party Agreement Hanford Public Involvement Plan

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    from the Comment and Response Document on the Tri-Party Agreement Hanford Public Involvement Plan The comments submitted by the Hanford Advisory Board (Advice 251) were...

  8. Tri-Party Agreement Agencies - Public involvement calendar -...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    TRI-PARTY AGREEMENT AGENCIES - PUBLIC INVOLVEMENT CALENDAR - FISCAL YEAR 2015 - SEPTEMBER 2015 EVENTS IN PROGRESSCOMING SOON September 2015 October 2015 November 2015 Tri-Party...

  9. FOIASI - Special Inquiry Review of Allegations InvolvingPotentialMisc...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    The allegations involved potential violations of political activity restrictions, lack of impartiality in performing official duties, misuse of position, and other related ...

  10. Lithium-vanadium advanced blanket development. ITER final report on U.S. contribution: Task T219/T220

    SciTech Connect (OSTI)

    Smith, D.L.; Mattas, R.F.

    1997-07-01

    The objective of this task is to develop the required data base and demonstrate the performance of a liquid lithium-vanadium advanced blanket design. The task has two main activities related to vanadium structural material and liquid lithium system developments. The vanadium alloy development activity included four subtasks: (1.1) baseline mechanical properties of non irradiated base metal and weld metal joints; (1.2) compatibility with liquid lithium; (1.3) material irradiation tests; and (1.4) development of material manufacturing and joining methods. The lithium blanket technology activity included four subtasks: (2.1) electrical insulation development and testing for liquid metal systems; (2.2) MHD pressure drop and heat transfer study for self-cooled liquid metal systems; (2.3) chemistry of liquid lithium; and (2.4) design, fabrication and testing of ITER relevant size blanket mockups. A summary of the progress and results obtained during the period 1995 and 1996 in each of the subtask areas is presented in this report.

  11. Multi-layer Lanczos iteration approach to calculations of vibrational energies and dipole transition intensities for polyatomic molecules

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Yu, Hua-Gen

    2015-01-28

    We report a rigorous full dimensional quantum dynamics algorithm, the multi-layer Lanczos method, for computing vibrational energies and dipole transition intensities of polyatomic molecules without any dynamics approximation. The multi-layer Lanczos method is developed by using a few advanced techniques including the guided spectral transform Lanczos method, multi-layer Lanczos iteration approach, recursive residue generation method, and dipole-wavefunction contraction. The quantum molecular Hamiltonian at the total angular momentum J = 0 is represented in a set of orthogonal polyspherical coordinates so that the large amplitude motions of vibrations are naturally described. In particular, the algorithm is general and problem-independent. An applicationmore » is illustrated by calculating the infrared vibrational dipole transition spectrum of CH₄ based on the ab initio T8 potential energy surface of Schwenke and Partridge and the low-order truncated ab initio dipole moment surfaces of Yurchenko and co-workers. A comparison with experiments is made. The algorithm is also applicable for Raman polarizability active spectra.« less

  12. Prospects for measuring the fuel ion ratio in burning ITER plasmas using a DT neutron emission spectrometer

    SciTech Connect (OSTI)

    Hellesen, C.; Skiba, M., E-mail: mateusz.skiba@physics.uu.se; Dzysiuk, N.; Weiszflog, M.; Hjalmarsson, A.; Ericsson, G.; Conroy, S.; Andersson-Sundn, E.; Eriksson, J.; Binda, F. [Department of Physics and Astronomy, Uppsala University, Uppsala (EURATOM-VR Association), SE-75120 Uppsala (Sweden)

    2014-11-15

    The fuel ion ratio n{sub t}/n{sub d} is an essential parameter for plasma control in fusion reactor relevant applications, since maximum fusion power is attained when equal amounts of tritium (T) and deuterium (D) are present in the plasma, i.e., n{sub t}/n{sub d} = 1.0. For neutral beam heated plasmas, this parameter can be measured using a single neutron spectrometer, as has been shown for tritium concentrations up to 90%, using data obtained with the MPR (Magnetic Proton Recoil) spectrometer during a DT experimental campaign at the Joint European Torus in 1997. In this paper, we evaluate the demands that a DT spectrometer has to fulfill to be able to determine n{sub t}/n{sub d} with a relative error below 20%, as is required for such measurements at ITER. The assessment shows that a back-scattering time-of-flight design is a promising concept for spectroscopy of 14 MeV DT emission neutrons.

  13. THE CRYOPLANT FOR THE ITER NEUTRAL BEAM TEST FACILITY TO BE BUILT AT RFX IN PADOVA, ITALY

    SciTech Connect (OSTI)

    Pengo, R.; Fellin, F.; Sonato, P.

    2010-04-09

    The Neutral Beam Test Facility (NBTF), planned to be constructed in Padua (Italy), will constitute the prototype of the two Neutral Beam Injectors (NBI), which will be installed in the ITER plant (Cadarache-France). The NBTF is composed of a 1 MV accelerator that can produce a 40 A deuteron pulsed neutral beam particles. The necessary vacuum needed in the accelerator is achieved by two large cryopumps, designed by FZK-Karlsruhe, with radiation shields cooled between 65 K and 90 K and with cryopanels cooled by 4 bar supercritical helium (ScHe) between 4.5 K and 6.5 K. A new cryoplant facility will be installed with two large helium refrigerators: a Shield Refrigerator (SR), whose cooling capacity is up to 30 kW between 65 K and 90 K, and a helium Main Refrigerator (MR), whose equivalent cooling capacity is up to 800 W at 4.5 K. The cooling of the cryopanels is obtained with two (ScHe) 30 g/s pumps (one redundant), working in a closed cycle around 4 bar producing a pressure head of 100 mbar. Two heat exchangers are immersed in a buffer dewar connected to the MR. The MR and SR different operation modes are described in the paper, as well as the new cryoplant installation.

  14. A quantum energy transport model for semiconductor device simulation

    SciTech Connect (OSTI)

    Sho, Shohiro; Odanaka, Shinji

    2013-02-15

    This paper describes numerical methods for a quantum energy transport (QET) model in semiconductors, which is derived by using a diffusion scaling in the quantum hydrodynamic (QHD) model. We newly drive a four-moments QET model similar with a classical ET model. Space discretization is performed by a new set of unknown variables. Numerical stability and convergence are obtained by developing numerical schemes and an iterative solution method with a relaxation method. Numerical simulations of electron transport in a scaled MOSFET device are discussed. The QET model allows simulations of quantum confinement transport, and nonlocal and hot-carrier effects in scaled MOSFETs.

  15. Multidomain Carbohydrate-binding Proteins Involved in Bacteroides

    Office of Scientific and Technical Information (OSTI)

    thetaiotaomicron Starch Metabolism (Journal Article) | SciTech Connect Multidomain Carbohydrate-binding Proteins Involved in Bacteroides thetaiotaomicron Starch Metabolism Citation Details In-Document Search Title: Multidomain Carbohydrate-binding Proteins Involved in Bacteroides thetaiotaomicron Starch Metabolism Authors: Cameron, Elizabeth A. ; Maynard, Mallory A. ; Smith, Christopher J. ; Smith, Thomas J. ; Koropatkin, Nicole M. ; Martens, Eric C. [1] ; Danforth) [2] + Show Author

  16. SU-E-T-583: Optimizing the MLC Model Parameters for IMRT in the RayStation Treatment Planning System

    SciTech Connect (OSTI)

    Chen, S; Yi, B; Xu, H; Yang, X; Prado, K; D'Souza, W

    2014-06-01

    Purpose: To optimize the MLC model parameters for IMRT in the RayStation v.4.0 planning system and for a Varian C-series Linac with a 120-leaf Millennium MLC. Methods: The RayStation treatment planning system models rounded leaf-end MLC with the following parameters: average transmission, leaf-tip width, tongue-and-groove, and position offset. The position offset was provided by Varian. The leaf-tip width was iteratively evaluated by comparing computed and measured transverse dose profiles of MLC-defined fields at dmax in water. The profile comparison was also used to verify the MLC position offset. The transmission factor and leaf tongue width were derived iteratively by optimizing five clinical patient IMRT QA Results: brain, lung, pancreas, head-and-neck (HN), and prostate. The HN and prostate cases involved splitting fields. Verifications were performed with Mapcheck2 measurements and Monte Carlo calculations. Finally, the MLC model was validated using five test IMRT cases from the AAPM TG119 report. Absolute gamma analyses (3mm/3% and 2mm/2%) were applied. In addition, computed output factors for MLC-defined small fields (22, 33, 44, 66cm) of both 6MV and 18MV were compared to those measured by the Radiological Physics Center (RPC). Results: Both 6MV and 18MV models were determined to have the same MLC parameters: 2.5% transmission, tongue-and-groove 0.05cm, and leaftip 0.3cm. IMRT QA analysis for five cases in TG119 resulted in a 100% passing rate with 3mm/3% gamma analysis for 6MV, and >97.5% for 18MV. With 2mm/2% gamma analysis, the passing rate was >94.6% for 6MV and >90.9% for 18MV. The difference between computed output factors in RayStation and RPC measurements was less than 2% for all MLCdefined fields, which meets the RPC's acceptance criterion. Conclusion: The rounded leaf-end MLC model in RayStation 4.0 planning system was verified and IMRT commissioning was clinically acceptable. The IMRT commissioning was well validated using guidance from the AAPMTG119 protocol.

  17. Alpha image reconstruction (AIR): A new iterative CT image reconstruction approach using voxel-wise alpha blending

    SciTech Connect (OSTI)

    Hofmann, Christian; Sawall, Stefan; Knaup, Michael; Kachelrieß, Marc

    2014-06-15

    Purpose: Iterative image reconstruction gains more and more interest in clinical routine, as it promises to reduce image noise (and thereby patient dose), to reduce artifacts, or to improve spatial resolution. Among vendors and researchers, however, there is no consensus of how to best achieve these aims. The general approach is to incorporatea priori knowledge into iterative image reconstruction, for example, by adding additional constraints to the cost function, which penalize variations between neighboring voxels. However, this approach to regularization in general poses a resolution noise trade-off because the stronger the regularization, and thus the noise reduction, the stronger the loss of spatial resolution and thus loss of anatomical detail. The authors propose a method which tries to improve this trade-off. The proposed reconstruction algorithm is called alpha image reconstruction (AIR). One starts with generating basis images, which emphasize certain desired image properties, like high resolution or low noise. The AIR algorithm reconstructs voxel-specific weighting coefficients that are applied to combine the basis images. By combining the desired properties of each basis image, one can generate an image with lower noise and maintained high contrast resolution thus improving the resolution noise trade-off. Methods: All simulations and reconstructions are performed in native fan-beam geometry. A water phantom with resolution bar patterns and low contrast disks is simulated. A filtered backprojection (FBP) reconstruction with a Ram-Lak kernel is used as a reference reconstruction. The results of AIR are compared against the FBP results and against a penalized weighted least squares reconstruction which uses total variation as regularization. The simulations are based on the geometry of the Siemens Somatom Definition Flash scanner. To quantitatively assess image quality, the authors analyze line profiles through resolution patterns to define a contrast factor for contrast-resolution plots. Furthermore, the authors calculate the contrast-to-noise ratio with the low contrast disks and the authors compare the agreement of the reconstructions with the ground truth by calculating the normalized cross-correlation and the root-mean-square deviation. To evaluate the clinical performance of the proposed method, the authors reconstruct patient data acquired with a Somatom Definition Flash dual source CT scanner (Siemens Healthcare, Forchheim, Germany). Results: The results of the simulation study show that among the compared algorithms AIR achieves the highest resolution and the highest agreement with the ground truth. Compared to the reference FBP reconstruction AIR is able to reduce the relative pixel noise by up to 50% and at the same time achieve a higher resolution by maintaining the edge information from the basis images. These results can be confirmed with the patient data. Conclusions: To evaluate the AIR algorithm simulated and measured patient data of a state-of-the-art clinical CT system were processed. It is shown, that generating CT images through the reconstruction of weighting coefficients has the potential to improve the resolution noise trade-off and thus to improve the dose usage in clinical CT.

  18. Best Practices for Emergency Response to Incidents Involving...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    -- Page iii -- FOREWORD Fires involving cars, trucks and other highway vehicles are a ... and PPE 194 8.2.1 General Procedures for Hybrid and EDV Fire Suppression 194 8.2.2 ...

  19. Getting Involved in Manufacturing Day – College Educators Edition Webinar

    Broader source: Energy.gov [DOE]

    This webinar will help address questions on why and how community colleges, universities, and technical schools can get involved with MFG DAY.  Led by MFG DAY Co-Producers, the webinar will also...

  20. Drum Involved in Idaho Incident Not Shippable to WIPP

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    The drum involved in the venting incident was not shippable to WIPP as packaged. Sealed drums cannot be shipped to WIPP without venting. The drum in the incident had been sealed...

  1. Global prevalence and distribution of genes and microorganisms involved in

    Office of Scientific and Technical Information (OSTI)

    mercury methylation (Journal Article) | DOE PAGES Global prevalence and distribution of genes and microorganisms involved in mercury methylation « Prev Next » Title: Global prevalence and distribution of genes and microorganisms involved in mercury methylation Mercury methylation produces the neurotoxic, highly bioaccumulative methylmercury (MeHg). Recent identification of the methylation genes (hgcAB) provides the foundation for broadly evaluating microbial Hg-methylation potential in

  2. Integrated Analysis of Protein Complexes and Regulatory Networks Involved

    Office of Scientific and Technical Information (OSTI)

    in Anaerobic Energy Metabolism of Shewanella Oneidensis MR-1 (Technical Report) | SciTech Connect Technical Report: Integrated Analysis of Protein Complexes and Regulatory Networks Involved in Anaerobic Energy Metabolism of Shewanella Oneidensis MR-1 Citation Details In-Document Search Title: Integrated Analysis of Protein Complexes and Regulatory Networks Involved in Anaerobic Energy Metabolism of Shewanella Oneidensis MR-1 Anaerobic Nitrate Reduction. Nitrate is an extensive co-contaminant

  3. Memory and Spin Injection Devices Involving Half Metals (Journal Article) |

    Office of Scientific and Technical Information (OSTI)

    SciTech Connect Memory and Spin Injection Devices Involving Half Metals Citation Details In-Document Search Title: Memory and Spin Injection Devices Involving Half Metals Authors: Shaughnessy, M. ; Snow, Ryan ; Damewood, L. ; Fong, C. Y. Publication Date: 2011-01-01 OSTI Identifier: 1198038 Grant/Contract Number: AC52-07NA27344 Type: Published Article Journal Name: Journal of Nanomaterials Additional Journal Information: Journal Volume: 2011; Journal ID: ISSN 1687-4110 Publisher: Hindawi

  4. NEPA-Related Public Involvement | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    NEPA-Related Public Involvement NEPA-Related Public Involvement The Loan Programs Office's NEPA-related hearings, public meetings, and public notices (e.g. public scoping meeting, public hearing, notice of proposed floodplain or wetland action) are presented below under NEPA-Related Hearings, Meetings, and Notices. Available environmental documents can be found at the following links: Categorical Exclusions Environmental Assessments Environmental Impact Statements NEPA-Related Hearings,

  5. Accurate Numerical Simulations Of Chemical Phenomena Involved in Energy

    Office of Scientific and Technical Information (OSTI)

    Production and Storage with MADNESS and MPQC: ALCF-2 Early Science Program Technical Report (Technical Report) | SciTech Connect Technical Report: Accurate Numerical Simulations Of Chemical Phenomena Involved in Energy Production and Storage with MADNESS and MPQC: ALCF-2 Early Science Program Technical Report Citation Details In-Document Search Title: Accurate Numerical Simulations Of Chemical Phenomena Involved in Energy Production and Storage with MADNESS and MPQC: ALCF-2 Early Science

  6. Get Involved with Home Energy Score | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Home Energy Score » Get Involved with Home Energy Score Get Involved with Home Energy Score The Department of Energy's (DOE) Home Energy Score helps homeowners understand the energy performance of their homes and how they compare to other homes nationwide. Energy professionals and organizations can use the Score to promote energy efficiency to homeowners and encourage investments in energy improvements. Information for Homeowners Information for Interested Organizations Information for

  7. Metaproteomics Identifies the Protein Machinery Involved in Metal and

    Office of Scientific and Technical Information (OSTI)

    Radionuclide Reduction in Subsurface Microbiomes and Elucidates Mechanisms and U(VI) Reduction Immobilization (Technical Report) | SciTech Connect Technical Report: Metaproteomics Identifies the Protein Machinery Involved in Metal and Radionuclide Reduction in Subsurface Microbiomes and Elucidates Mechanisms and U(VI) Reduction Immobilization Citation Details In-Document Search Title: Metaproteomics Identifies the Protein Machinery Involved in Metal and Radionuclide Reduction in Subsurface

  8. Consistent analysis of one-nucleon spectroscopic factors involving weakly-

    Office of Scientific and Technical Information (OSTI)

    and strongly-bound nucleons (Journal Article) | SciTech Connect Consistent analysis of one-nucleon spectroscopic factors involving weakly- and strongly-bound nucleons Citation Details In-Document Search Title: Consistent analysis of one-nucleon spectroscopic factors involving weakly- and strongly-bound nucleons Authors: Okołowicz, J. ; Lam, Y. H. ; Płoszajczak, M. ; Macchiavelli, A. O. ; Smirnova, N. A. Publication Date: 2016-04-01 OSTI Identifier: 1246192 Grant/Contract Number:

  9. Emergency Response to a Transportation Accident Involving Radioactive

    Office of Environmental Management (EM)

    Material | Department of Energy Response to a Transportation Accident Involving Radioactive Material Emergency Response to a Transportation Accident Involving Radioactive Material The purpose of this User's Guide is to provide instructors with an overview of the key points covered in the video. The Student Handout portion of this Guide is designed to assist the instructor in reviewing those points with students. The Student Handout should be distributed to students after the video is shown

  10. Draft Public Involvement Advice for Central Plateau Cleanup

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    V0, 12/9/14 Draft Public Involvement Advice for Central Plateau Cleanup Principles Issue managers: Pollet, Mattson, Vanni, Plahuta, Catrell Background The Tri-Party Agencies are developing principles that will guide the cleanup of Hanford's Central Plateau. The Hanford Advisory Board (HAB) believes that the broader public should be involved in the development of these principles. Hanford's Central Plateau is planned to be the final footprint of the Hanford Site. The Central Plateau contains

  11. Icing modelling in NSMB with chimera overset grids

    SciTech Connect (OSTI)

    Pena, D.; Deloze, T.; Laurendeau, E.; Hoarau, Y.

    2015-03-10

    In aerospace Engineering, the accurate simulation of ice accretion is a key element to increase flight safety and avoid accidents related to icing effects. The icing code developed in the NSMB solver is based on an Eulerian formulation for droplets tracking, an iterative Messinger model using a modified water runback scheme for ice thickness calculation and mesh deformation to track the ice/air interface through time. The whole process is parallelized with MPI and applied with chimera grids.

  12. US ITER - Why Fusion?

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    US Fusion Research Sites US Fusion Research Sites DOE Office of Science: US Fusion Energy Sciences Program Fusion Power Associates General Atomics DIIII-D National Fusion Facility Georgia Tech: Fusion Research Center Lawrence Livermore National Laboratory: National Ignition Facility Los Alamos National Laboratory: Fusion Energy Sciences MIT: Plasma Science and Fusion Center Naval Research Laboratory: Plasma Physics Division Oak Ridge National Laboratory: Fusion Energy Division Princeton Plasma

  13. US ITER | Doing Business

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    US: Business Opportunities with Other Partner Laboratories US: Business Opportunities with Other Partner Laboratories Princeton Plasma Physics Laboratory (PPPL): Companies and institutions that wish to provide design and R&D support and participate in the supply of materials and supplies through a Subcontract with the PPPL should review tender documents for the procurements listed below at PPPL Procurement Opportunities. Please direct any questions, correspondence or submissions to the PPPL

  14. US ITER Vendor Information

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    multiple selections Select Keywords for Products and Services You Supply Building Materials Chemicals and Allied Products Clothing and Apparel Commercial Economic,...

  15. Photo: US ITER

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    strand * High Performance Magnetics, Tallahassee, FL; Toroidal Field conductor ... Petersburg * Tallahassee * Winter Springs Georgia Alpharetta * Atlanta * Cumming * Duluth ...

  16. US ITER | About

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Disruption Mitigation System Disruption Mitigation System (WBS 1.3.1) Fact Sheet The US will contribute 100% towards the disruption mitigation system. The system has two functions: 1) limiting the impacts of plasma current disruptions to the tokamak vacuum vessel, first wall blankets and other in-vessel components, and 2) suppressing the formation and deleterious effects of high energy runaway electrons. The mitigation and suppression are expected to be accomplished by rapid massive pellet

  17. US ITER | About

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Short-Term Accommodations Short-Term Accommodations If your stay will be brief, Oak Ridge hotel/motel accommodations are available. Several major hotel chains offer suites with kitchen facilities. It is best to make reservations as soon as possible. Check for discount rates for students, government employees, and travel association members. You will be required to supply your identification card to receive the discounted rate. Additional accommodations are available in Knoxville. If you plan to

  18. US ITER | About

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Area Guides Area Guides Oak Ridge Oak Ridge Chamber of Commerce Oak Ridge Convention and Visitors Bureau Knoxville City About Knoxville Knoxville Convention & Visitors Bureau Knoxville Chamber of Commerce Knoxville Community Info Knox County Anderson County Lenoir City Loudon County Tennessee

  19. US ITER | About

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Food Food Oak Ridge and Knoxville offer a variety of places to dine out. Knoxville, being a larger city, has more variety. Check the Oak Ridge Convention and Visitors Bureau for Oak Ridge restaurants oakridgevisitor.com/dining.html. Most Oak Ridge restaurants are located on the Oak Ridge Turnpike (Hwy 95) or Illinois Avenue and are open until 10:00 p.m. Check the telephone directory yellow pages for listings. Most of these restaurants don't take reservations. The Doubletree Hotel is the only

  20. US ITER | About

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Local Media Local Media Newspapers Metro Pulse Weekly Newspaper The Oak Ridger The Knoxville News Sentinel The Roane County News TV Stations WATE WBIR WVLT The purpose of this web site is to help you acquire basic information and contacts that will enhance your stay in the area. Please feel free to contact us with any questions or comments at webmaster@usiter.org

  1. US ITER | About

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Weather Weather There's a saying around here, "If you don't like the weather, stick around, it will change." We celebrate all four seasons in East Tennessee. Spring and fall are mild and colorful. Summer can be warm and humid; winters are brief and mild. Annual average temperature: high 69°F; low 46°F Average low temperature: January, 26°F; July, 66°F Average high temperature: January, 46°F; July, 87°F Annual average precipitation: 47.14 inches Annual average snowfall: 11.4

  2. US ITER | Media Corner

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    novel three-barrel pellet injector for delivering the pellets to the plasma. The pellet guns use a gas propellant to fire pellets at 300 meters per second, or about 670 miles per...

  3. Community assessments: Road maps to successful public involvement

    SciTech Connect (OSTI)

    Forrest, C.J.

    1995-12-01

    This paper presents a framework for performing comprehensive community assessments to increase the effectiveness of public involvement efforts. The community assessment process involves systematic and critical examination of beliefs, attitudes, opinions and knowledge of the many groups in the community. A good community assessment gathers information on the concerns or issues directly related to an environmental project as well as other important community issues to ensure development of an effective public involvement program. The framework discusses types of people and organizations that should be included in the community assessment interview process. It also delineates steps that persons charged with performing assessments can take to ensure that the views of all potential stakeholders are included--a necessary consideration in communities that are ethnically, racially, or economically diverse. Lastly, the framework discusses types of written materials that can be analyzed for additional insight into communities. For example, it discusses methods for reviewing past issues of the local newspaper to provide both validation of the information gathered during interviews and an understanding of the ways that community members give and receive information and respond to conflict or perceived threats. This framework is designed to show environmental professionals who are responsible for public involvement how to perform an initial community assessment. It provides illustrations of instances in which information vital to a successful public involvement effort has been uncovered through a careful assessment of the community. Both the U.S. EPA and the public have made clear their intentions to require increased public involvement. Many of these efforts will succeed or fail based on how well those charged with the public involvement component of environmental projects identify community issues and design communications programs that successfully reach all stakeholders.

  4. Renormalization group flow and fixed point of the lattice topological charge in the 2D O(3) {sigma} model

    SciTech Connect (OSTI)

    DElia, M.; Farchioni, F.; Papa, A.

    1997-02-01

    We study the renormalization group evolution up to the fixed point of the lattice topological susceptibility in the 2D O(3) nonlinear {sigma} model. We start with a discretization of the continuum topological charge by a local charge density polynomial in the lattice fields. Among the different choices we propose also a Symanzik-improved lattice topological charge. We check step by step in the renormalization group iteration the progressive dumping of quantum fluctuations, which are responsible for the additive and multiplicative renormalizations of the lattice topological susceptibility with respect to the continuum definition. We find that already after three iterations these renormalizations are negligible and an excellent approximation of the fixed point is achieved. We also check by an explicit calculation that the assumption of slowly varying fields in iterating the renormalization group does not lead to a good approximation of the fixed point charge operator. {copyright} {ital 1997} {ital The American Physical Society}

  5. TH-C-18A-01: Is Automatic Tube Current Modulation Still Necessary with Statistical Iterative Reconstruction?

    SciTech Connect (OSTI)

    Li, K; Zhao, W; Gomez-Cardona, D; Chen, G

    2014-06-15

    Purpose: Automatic tube current modulation (TCM) has been widely used in modern multi-detector CT to reduce noise spatial nonuniformity and streaks to improve dose efficiency. With the advent of statistical iterative reconstruction (SIR), it is expected that the importance of TCM may diminish, since SIR incorporates statistical weighting factors to reduce the negative influence of photon-starved rays. The purpose of this work is to address the following questions: Does SIR offer the same benefits as TCM? If yes, are there still any clinical benefits to using TCM? Methods: An anthropomorphic CIRS chest phantom was scanned using a state-of-the-art clinical CT system equipped with an SIR engine (Veo, GE Healthcare). The phantom was first scanned with TCM using a routine protocol and a low-dose (LD) protocol. It was then scanned without TCM using the same protocols. For each acquisition, both FBP and Veo reconstructions were performed. All scans were repeated 50 times to generate an image ensemble from which noise spatial nonuniformity (NSN) and streak artifact levels were quantified. Monte-Carlo experiments were performed to estimate skin dose. Results: For FBP, noise streaks were reduced by 4% using TCM for both routine and LD scans. NSN values were actually slightly higher with TCM (0.25) than without TCM (0.24) for both routine and LD scans. In contrast, for Veo, noise streaks became negligible (<1%) with or without TCM for both routine and LD scans, and the NSN was reduced to 0.10 (low dose) or 0.08 (routine). The overall skin dose was 2% lower at the shoulders and more uniformly distributed across the skin without TCM. Conclusion: SIR without TCM offers superior reduction in noise nonuniformity and streaks relative to FBP with TCM. For some clinical applications in which skin dose may be a concern, SIR without TCM may be a better option. K. Li, W. Zhao, D. Gomez-Cardona: Nothing to disclose; G.-H. Chen: Research funded, General Electric Company Research funded, Siemens AG Research funded, Varian Medical Systems, Research funded, Hologic, Inc.

  6. Model Selection for Monitoring CO2 Plume during Sequestration

    Energy Science and Technology Software Center (OSTI)

    2014-12-31

    The model selection method developed as part of this project mainly includes four steps: (1) assessing the connectivity/dynamic characteristics of a large prior ensemble of models, (2) model clustering using multidimensional scaling coupled with k-mean clustering, (3) model selection using the Bayes' rule in the reduced model space, (4) model expansion using iterative resampling of the posterior models. The fourth step expresses one of the advantages of the method: it provides a built-in means ofmore » quantifying the uncertainty in predictions made with the selected models. In our application to plume monitoring, by expanding the posterior space of models, the final ensemble of representations of geological model can be used to assess the uncertainty in predicting the future displacement of the CO2 plume. The software implementation of this approach is attached here.« less

  7. Development of a Spatially Resolving X-Ray Crystal Spectrometer For Measurement of Ion-temprature (Ti) And Rotation-velocity (v) Profiles in ITER

    Office of Scientific and Technical Information (OSTI)

    1 PPPL- 4581 Development of a Spatially Resolving X-Ray Crystal Spectrometer For Measurement of Ion-temprature (Ti) And Rotation-velocity (v) Profiles in ITER December, 2010 K. W. Hill, M. Bitter, L. Delgado-Aparicio, D. Johnson, R. Feder, P. Beiersdorfer, J. Dunn, K. Morris, E. Wang, M. Reinke, Y. Podpaly, J. E. Rice, R. Barnsley, M. O'Mullane, and S. G. Lee Princeton Plasma Physics Laboratory Report Disclaimers Full Legal Disclaimer This report was prepared as an account of work sponsored by

  8. Multivariate Calibration Models for Sorghum Composition using Near-Infrared Spectroscopy

    SciTech Connect (OSTI)

    Wolfrum, E.; Payne, C.; Stefaniak, T.; Rooney, W.; Dighe, N.; Bean, B.; Dahlberg, J.

    2013-03-01

    NREL developed calibration models based on near-infrared (NIR) spectroscopy coupled with multivariate statistics to predict compositional properties relevant to cellulosic biofuels production for a variety of sorghum cultivars. A robust calibration population was developed in an iterative fashion. The quality of models developed using the same sample geometry on two different types of NIR spectrometers and two different sample geometries on the same spectrometer did not vary greatly.

  9. Final report on the public involvement process phase 1, Monitored Retrievable Storage Facility Feasibility Study

    SciTech Connect (OSTI)

    Moore, L.; Shanteau, C.

    1992-12-01

    This report summarizes the pubic involvement component of Phase 1 of the Monitored Retrievable Storage Facility (NM) Feasibility Study in San Juan County, Utah. Part of this summary includes background information on the federal effort to locate a voluntary site for temporary storage of nuclear waste, how San Juan County came to be involved, and a profile of the county. The heart of the report, however, summarizes the activities within the public involvement process, and the issues raised in those various forums. The authors have made every effort to reflect accurately and thoroughly all the concerns and suggestions expressed to us during the five month process. We hope that this report itself is a successful model of partnership with the citizens of the county -- the same kind of partnership the county is seeking to develop with its constituents. Finally, this report offers some suggestions to both county officials and residents alike. These suggestions concern how decision-making about the county's future can be done by a partnership of informed citizens and listening decision-makers. In the Appendix are materials relating to the public involvement process in San Juan County.

  10. Final report on the public involvement process phase 1, Monitored Retrievable Storage Facility Feasibility Study

    SciTech Connect (OSTI)

    Moore, L.; Shanteau, C.

    1992-12-01

    This report summarizes the pubic involvement component of Phase 1 of the Monitored Retrievable Storage Facility (NM) Feasibility Study in San Juan County, Utah. Part of this summary includes background information on the federal effort to locate a voluntary site for temporary storage of nuclear waste, how San Juan County came to be involved, and a profile of the county. The heart of the report, however, summarizes the activities within the public involvement process, and the issues raised in those various forums. The authors have made every effort to reflect accurately and thoroughly all the concerns and suggestions expressed to us during the five month process. We hope that this report itself is a successful model of partnership with the citizens of the county -- the same kind of partnership the county is seeking to develop with its constituents. Finally, this report offers some suggestions to both county officials and residents alike. These suggestions concern how decision-making about the county`s future can be done by a partnership of informed citizens and listening decision-makers. In the Appendix are materials relating to the public involvement process in San Juan County.

  11. OSPREY Model

    SciTech Connect (OSTI)

    Veronica J. Rutledge

    2013-01-01

    The absence of industrial scale nuclear fuel reprocessing in the U.S. has precluded the necessary driver for developing the advanced simulation capability now prevalent in so many other countries. Thus, it is essential to model complex series of unit operations to simulate, understand, and predict inherent transient behavior and feedback loops. A capability of accurately simulating the dynamic behavior of advanced fuel cycle separation processes will provide substantial cost savings and many technical benefits. The specific fuel cycle separation process discussed in this report is the off-gas treatment system. The off-gas separation consists of a series of scrubbers and adsorption beds to capture constituents of interest. Dynamic models are being developed to simulate each unit operation involved so each unit operation can be used as a stand-alone model and in series with multiple others. Currently, an adsorption model has been developed within Multi-physics Object Oriented Simulation Environment (MOOSE) developed at the Idaho National Laboratory (INL). Off-gas Separation and REcoverY (OSPREY) models the adsorption of off-gas constituents for dispersed plug flow in a packed bed under non-isothermal and non-isobaric conditions. Inputs to the model include gas, sorbent, and column properties, equilibrium and kinetic data, and inlet conditions. The simulation outputs component concentrations along the column length as a function of time from which breakthrough data is obtained. The breakthrough data can be used to determine bed capacity, which in turn can be used to size columns. It also outputs temperature along the column length as a function of time and pressure drop along the column length. Experimental data and parameters were input into the adsorption model to develop models specific for krypton adsorption. The same can be done for iodine, xenon, and tritium. The model will be validated with experimental breakthrough curves. Customers will be given access to OSPREY to used and evaluate the model.

  12. Boltzmann-Electron Model in Aleph.

    SciTech Connect (OSTI)

    Hughes, Thomas Patrick; Hooper, Russell

    2014-11-01

    We apply the Boltzmann-electron model in the electrostatic, particle-in-cell, finite- element code Aleph to a plasma sheath. By assuming a Boltzmann energy distribution for the electrons, the model eliminates the need to resolve the electron plasma fre- quency, and avoids the numerical %22grid instability%22 that can cause unphysical heating of electrons. This allows much larger timesteps to be used than with kinetic electrons. Ions are treated with the standard PIC algorithm. The Boltzmann-electron model re- quires solution of a nonlinear Poisson equation, for which we use an iterative Newton solver (NOX) from the Trilinos Project. Results for the spatial variation of density and voltage in the plasma sheath agree well with an analytic model

  13. GC GUIDANCE ON BARTER TRANSACTIONS INVOLVING DOE-OWNED URANIUM

    Energy Savers [EERE]

    GC GUIDANCE ON BARTER TRANSACTIONS INVOLVING DOE-OWNED URANIUM The Department of Energy has on a variety of occasions engaged in transactions under which it bartered uranium to which it has title for goods or services . This guidance memorializes the results of analyses previously directed to individual proposed transactions . For the reasons discussed below, we conclude that the Atomic Energy Act of 1954' , as amended, (AEA), authorizes such barter transactions. Background : DOE Barter

  14. Tri-Party Agreement Agencies Annual Hanford Public Involvement Survey

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    7 Tri-Party Agreement Agencies Annual Hanford Public Involvement Survey 1. How do you usually receive information about Hanford topics? (Please select all that apply) Response Percent Response Count Advisory Board 23.7% 22 Citizens Group 32.3% 30 Ecology website 21.5% 20 Hanford.gov website 33.3% 31 Hanford Listserv (email) 54.8% 51 Hanford Mailing (postal) 12.9% 12 Newspaper 48.4% 45 Radio 26.9% 25 Social Media (Facebook, Twitter, etc.) 26.9% 25 Television 17.2% 16 Work Announcements 11.8% 11 I

  15. Probative Investigation of the Thermal Stability of Wastes Involved in

    Energy Savers [EERE]

    ProActive DNS Blacklisting ProActive DNS Blacklisting PDF icon Tuesday_Fair_Park_2_1330_Rackow.pdf More Documents & Publications DNS as a Covert Channel Within Protected Networks Cyber Security Procurement Language for Control Systems Version 1.8 Slide February 2014 Waste Isolation Pilot Plant (WIPP) Waste Drum Breach Event | Department of Energy

    Probative Investigation of the Thermal Stability of Wastes Involved in February 2014 Waste Isolation Pilot Plant (WIPP) Waste Drum Breach

  16. Central Plateau Principles Public Involvement Advice DETAILED BACKGROUND

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    v0, 12/9/14 Central Plateau Principles Public Involvement Advice DETAILED BACKGROUND Cleanup of Hanford's Central Plateau is expected to take another four decades or longer, and cost tens of billions of dollars. The Central Plateau includes the 200 East and 200 West Areas with all of Hanford's High-Level Nuclear Waste Tank Farms, processing plants, sites where over a million gallons of High-Level Nuclear Waste has leaked from Single Shell Tanks (SSTs), and billions of gallons of waste was

  17. Antitrust aspects of involvement by utilities in residential solar energy

    SciTech Connect (OSTI)

    Hurst, T.R.

    1983-01-01

    A utility that merely engages in the sale of solar units produced by independent manufacturers on a nonexclusive basis appears to run little risk of violating federal antitrust laws, but virtually every other unregulated activity would involve enough significant exposure to antitrust liability to preclude a prudent utility from engaging in them on any basis other than one where the state-action exemption clearly shields the utility. The case cited in this review indicates that municipal utilities must be equally cautious when engaging in pro-solar activities that may have an anticompetitive impact on various parties who could become plaintiffs in a private antitrust action. 47 references.

  18. Report on International Collaboration Involving the FE Heater and HG-A Tests at Mont Terri

    SciTech Connect (OSTI)

    Houseworth, Jim; Rutqvist, Jonny; Asahina, Daisuke; Chen, Fei; Vilarrasa, Victor; Liu, Hui-Hai; Birkholzer, Jens

    2013-11-06

    Nuclear waste programs outside of the US have focused on different host rock types for geological disposal of high-level radioactive waste. Several countries, including France, Switzerland, Belgium, and Japan are exploring the possibility of waste disposal in shale and other clay-rich rock that fall within the general classification of argillaceous rock. This rock type is also of interest for the US program because the US has extensive sedimentary basins containing large deposits of argillaceous rock. LBNL, as part of the DOE-NE Used Fuel Disposition Campaign, is collaborating on some of the underground research laboratory (URL) activities at the Mont Terri URL near Saint-Ursanne, Switzerland. The Mont Terri project, which began in 1995, has developed a URL at a depth of about 300 m in a stiff clay formation called the Opalinus Clay. Our current collaboration efforts include two test modeling activities for the FE heater test and the HG-A leak-off test. This report documents results concerning our current modeling of these field tests. The overall objectives of these activities include an improved understanding of and advanced relevant modeling capabilities for EDZ evolution in clay repositories and the associated coupled processes, and to develop a technical basis for the maximum allowable temperature for a clay repository. The R&D activities documented in this report are part of the work package of natural system evaluation and tool development that directly supports the following Used Fuel Disposition Campaign (UFDC) objectives: ? Develop a fundamental understanding of disposal-system performance in a range of environments for potential wastes that could arise from future nuclear-fuel-cycle alternatives through theory, simulation, testing, and experimentation. ? Develop a computational modeling capability for the performance of storage and disposal options for a range of fuel-cycle alternatives, evolving from generic models to more robust models of performance assessment. For the purpose of validating modeling capabilities for thermal-hydro-mechanical (THM) processes, we developed a suite of simulation models for the planned full-scale FE Experiment to be conducted in the Mont Terri URL, including a full three-dimensional model that will be used for direct comparison to experimental data once available. We performed for the first time a THM analysis involving the Barcelona Basic Model (BBM) in a full three-dimensional field setting for modeling the geomechanical behavior of the buffer material and its interaction with the argillaceous host rock. We have simulated a well defined benchmark that will be used for codeto- code verification against modeling results from other international modeling teams. The analysis highlights the complex coupled geomechanical behavior in the buffer and its interaction with the surrounding rock and the importance of a well characterized buffer material in terms of THM properties. A new geomechanical fracture-damage model, TOUGH-RBSN, was applied to investigate damage behavior in the ongoing HG-A test at Mont Terri URL. Two model modifications have been implemented so that the Rigid-Body-Spring-Network (RBSN) model can be used for analysis of fracturing around the HG-A microtunnel. These modifications are (1) a methodology to compute fracture generation under compressive stress conditions and (2) a method to represent anisotropic elastic and strength properties. The method for computing fracture generation under compressive load produces results that roughly follow trends expected for homogeneous and layered systems. Anisotropic properties for the bulk rock were represented in the RBSN model using layered heterogeneity and gave bulk material responses in line with expectations. These model improvements were implemented for an initial model of fracture damage at the HG-A test. While the HG-A test model results show some similarities with the test observations, differences between the model results and observations remain.

  19. Model Wind Ordinance for Local Governments

    Broader source: Energy.gov [DOE]

    In 2006, Pennsylvania developed a model local ordinance for wind energy facilities through a collaborative effort involving several state departments and stakeholder groups. The purpose of the...

  20. Decoupling and Utility Business Model Resources

    Broader source: Energy.gov [DOE]

    Energy efficiency measures result in decreased energy use, which may be contrary to a utility whose business model involves increasing revenue through increased energy demand.

  1. Spectral restoration in high resolution electron energy loss spectroscopy based on iterative semi-blind Lucy-Richardson algorithm applied to rutile surfaces

    SciTech Connect (OSTI)

    Lazzari, Rmi Li, Jingfeng Jupille, Jacques

    2015-01-15

    A new spectral restoration algorithm of reflection electron energy loss spectra is proposed. It is based on the maximum likelihood principle as implemented in the iterative Lucy-Richardson approach. Resolution is enhanced and point spread function recovered in a semi-blind way by forcing cyclically the zero loss to converge towards a Dirac peak. Synthetic phonon spectra of TiO{sub 2} are used as a test bed to discuss resolution enhancement, convergence benefit, stability towards noise, and apparatus function recovery. Attention is focused on the interplay between spectral restoration and quasi-elastic broadening due to free carriers. A resolution enhancement by a factor up to 6 on the elastic peak width can be obtained on experimental spectra of TiO{sub 2}(110) and helps revealing mixed phonon/plasmon excitations.

  2. SU-E-I-82: Improving CT Image Quality for Radiation Therapy Using Iterative Reconstruction Algorithms and Slightly Increasing Imaging Doses

    SciTech Connect (OSTI)

    Noid, G; Chen, G; Tai, A; Li, X

    2014-06-01

    Purpose: Iterative reconstruction (IR) algorithms are developed to improve CT image quality (IQ) by reducing noise without diminishing spatial resolution or contrast. For CT in radiation therapy (RT), slightly increasing imaging dose to improve IQ may be justified if it can substantially enhance structure delineation. The purpose of this study is to investigate and to quantify the IQ enhancement as a result of increasing imaging doses and using IR algorithms. Methods: CT images were acquired for phantoms, built to evaluate IQ metrics including spatial resolution, contrast and noise, with a variety of imaging protocols using a CT scanner (Definition AS Open, Siemens) installed inside a Linac room. Representative patients were scanned once the protocols were optimized. Both phantom and patient scans were reconstructed using the Sinogram Affirmed Iterative Reconstruction (SAFIRE) and the Filtered Back Projection (FBP) methods. IQ metrics of the obtained CTs were compared. Results: IR techniques are demonstrated to preserve spatial resolution as measured by the point spread function and reduce noise in comparison to traditional FBP. Driven by the reduction in noise, the contrast to noise ratio is doubled by adopting the highest SAFIRE strength. As expected, increasing imaging dose reduces noise for both SAFIRE and FBP reconstructions. The contrast to noise increases from 3 to 5 by increasing the dose by a factor of 4. Similar IQ improvement was observed on the CTs for selected patients with pancreas and prostrate cancers. Conclusion: The IR techniques produce a measurable enhancement to CT IQ by reducing the noise. Increasing imaging dose further reduces noise independent of the IR techniques. The improved CT enables more accurate delineation of tumors and/or organs at risk during RT planning and delivery guidance.

  3. Market power and foreign involvement by US multinationals

    SciTech Connect (OSTI)

    Hirschey, M.

    1982-05-01

    This study considers the relationship between market power and multinational involvement through use of a market-valuation approach. Estimation results for a sample of large US multinationals reveal superior valuation effects due to returns from foreign as opposed to domestic operations. This finding is consistent with the hypothesis that returns from the US market tend to be less secure, and therefore less valued, than are returns from foreign markets due to both real (market size, entry barriers, etc.) and institutional (antitrust policies, etc.) differences in competitive environments. Such findings are also consistent with previous suggestions that firms develop markets abroad in order to exploit economic-rent opportunities. These findings remain tentative, however, and await verification in future studies of data from both the United States and abroad. 13 references, 1 table.

  4. Coupling a Reactive Transport Code with a Global Land Surface Model for Mechanistic Biogeochemistry Representation: 1. Addressing the Challenge of Nonnegativity

    SciTech Connect (OSTI)

    Tang, Guoping; Yuan, Fengming; Bisht, Gautam; Hammond, Glenn E.; Lichtner, Peter C.; Collier, Nathaniel O.; Kumar, Jitendra; Mills, Richard T.; Xu, Xiaofeng; Andre, Ben; Hoffman, Forrest M.; Painter, Scott L.; Thornton, Peter E.

    2016-01-01

    Reactive transport codes (e.g., PFLOTRAN) are increasingly used to improve the representation of biogeochemical processes in terrestrial ecosystem models (e.g., the Community Land Model, CLM). As CLM and PFLOTRAN use explicit and implicit time stepping, implementation of CLM biogeochemical reactions in PFLOTRAN can result in negative concentration, which is not physical and can cause numerical instability and errors. The objective of this work is to address the nonnegativity challenge to obtain accurate, efficient, and robust solutions. We illustrate the implementation of a reaction network with the CLM-CN decomposition, nitrification, denitrification, and plant nitrogen uptake reactions and test the implementation at arctic, temperate, and tropical sites. We examine use of scaling back the update during each iteration (SU), log transformation (LT), and downregulating the reaction rate to account for reactant availability limitation to enforce nonnegativity. Both SU and LT guarantee nonnegativity but with implications. When a very small scaling factor occurs due to either consumption or numerical overshoot, and the iterations are deemed converged because of too small an update, SU can introduce excessive numerical error. LT involves multiplication of the Jacobian matrix by the concentration vector, which increases the condition number, decreases the time step size, and increases the computational cost. Neither SU nor SE prevents zero concentration. When the concentration is close to machine precision or 0, a small positive update stops all reactions for SU, and LT can fail due to a singular Jacobian matrix. The consumption rate has to be downregulated such that the solution to the mathematical representation is positive. A first-order rate downregulates consumption and is nonnegative, and adding a residual concentration makes it positive. For zero-order rate or when the reaction rate is not a function of a reactant, representing the availability limitation of each reactant with a Monod substrate limiting function provides a smooth transition between a zero-order rate when the reactant is abundant and first-order rate when the reactant becomes limiting. When the half saturation is small, marching through the transition may require small time step sizes to resolve the sharp change within a small range of concentration values. Our results from simple tests and CLM-PFLOTRAN simulations caution against use of SU and indicate that accurate, stable, and relatively efficient solutions can be achieved with LT and downregulation with Monod substrate limiting function and residual concentration.

  5. Coupling a Reactive Transport Code with a Global Land Surface Model for Mechanistic Biogeochemistry Representation: 1. Addressing the Challenge of Nonnegativity

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Tang, Guoping; Yuan, Fengming; Bisht, Gautam; Hammond, Glenn E.; Lichtner, Peter C.; Collier, Nathaniel O.; Kumar, Jitendra; Mills, Richard T.; Xu, Xiaofeng; Andre, Ben; et al

    2016-01-01

    Reactive transport codes (e.g., PFLOTRAN) are increasingly used to improve the representation of biogeochemical processes in terrestrial ecosystem models (e.g., the Community Land Model, CLM). As CLM and PFLOTRAN use explicit and implicit time stepping, implementation of CLM biogeochemical reactions in PFLOTRAN can result in negative concentration, which is not physical and can cause numerical instability and errors. The objective of this work is to address the nonnegativity challenge to obtain accurate, efficient, and robust solutions. We illustrate the implementation of a reaction network with the CLM-CN decomposition, nitrification, denitrification, and plant nitrogen uptake reactions and test the implementation atmore » arctic, temperate, and tropical sites. We examine use of scaling back the update during each iteration (SU), log transformation (LT), and downregulating the reaction rate to account for reactant availability limitation to enforce nonnegativity. Both SU and LT guarantee nonnegativity but with implications. When a very small scaling factor occurs due to either consumption or numerical overshoot, and the iterations are deemed converged because of too small an update, SU can introduce excessive numerical error. LT involves multiplication of the Jacobian matrix by the concentration vector, which increases the condition number, decreases the time step size, and increases the computational cost. Neither SU nor SE prevents zero concentration. When the concentration is close to machine precision or 0, a small positive update stops all reactions for SU, and LT can fail due to a singular Jacobian matrix. The consumption rate has to be downregulated such that the solution to the mathematical representation is positive. A first-order rate downregulates consumption and is nonnegative, and adding a residual concentration makes it positive. For zero-order rate or when the reaction rate is not a function of a reactant, representing the availability limitation of each reactant with a Monod substrate limiting function provides a smooth transition between a zero-order rate when the reactant is abundant and first-order rate when the reactant becomes limiting. When the half saturation is small, marching through the transition may require small time step sizes to resolve the sharp change within a small range of concentration values. Our results from simple tests and CLM-PFLOTRAN simulations caution against use of SU and indicate that accurate, stable, and relatively efficient solutions can be achieved with LT and downregulation with Monod substrate limiting function and residual concentration.« less

  6. Cupola Furnace Computer Process Model

    SciTech Connect (OSTI)

    Seymour Katz

    2004-12-31

    The cupola furnace generates more than 50% of the liquid iron used to produce the 9+ million tons of castings annually. The cupola converts iron and steel into cast iron. The main advantages of the cupola furnace are lower energy costs than those of competing furnaces (electric) and the ability to melt less expensive metallic scrap than the competing furnaces. However the chemical and physical processes that take place in the cupola furnace are highly complex making it difficult to operate the furnace in optimal fashion. The results are low energy efficiency and poor recovery of important and expensive alloy elements due to oxidation. Between 1990 and 2004 under the auspices of the Department of Energy, the American Foundry Society and General Motors Corp. a computer simulation of the cupola furnace was developed that accurately describes the complex behavior of the furnace. When provided with the furnace input conditions the model provides accurate values of the output conditions in a matter of seconds. It also provides key diagnostics. Using clues from the diagnostics a trained specialist can infer changes in the operation that will move the system toward higher efficiency. Repeating the process in an iterative fashion leads to near optimum operating conditions with just a few iterations. More advanced uses of the program have been examined. The program is currently being combined with an ''Expert System'' to permit optimization in real time. The program has been combined with ''neural network'' programs to affect very easy scanning of a wide range of furnace operation. Rudimentary efforts were successfully made to operate the furnace using a computer. References to these more advanced systems will be found in the ''Cupola Handbook''. Chapter 27, American Foundry Society, Des Plaines, IL (1999).

  7. ABSTRACT: The Community Environmental Monitoring Program: Reducing Public Perception of Risk Through Stakeholder Involvement

    SciTech Connect (OSTI)

    T. Hartwell

    2007-02-28

    Between 1951 and 1992, 928 nuclear tests were conducted at the Nevada Test Site (NTS), including 100 atmospheric and 828 underground tests. Initial public reaction to the tests was largely supportive, but by the late 1950s this began to change, largely as a result of fear of the potential for adverse health effects to be caused by exposure to ionizing radiation resulting from the tests. The nuclear power plant accident at Three Mile Island in 1979 served to heighten these fears, as well as foster a general distrust of the federal agencies involved and low public confidence in monitoring results. Modeled after a similar program that involved the public in monitoring activities around the Three Mile Island nuclear power plant, the Community Environmental Monitoring Program (CEMP) has promoted stakeholder involvement, awareness, and understanding of radiological surveillance in communities surrounding the NTS since 1981. It involves stakeholders in the operation, data collection, and dissemination of information obtained from a network of 29 stations across a wide area of Nevada, Utah, and California. It is sponsored by the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) and administered by the Desert Research Institute (DRI) of the Nevada System of Higher Education. Since assuming administration of the program in 2000, DRI has accomplished significant enhancements to the network's data collection and transmission capabilities. A robust datalogging and communications system allows for the near real-time transmission of data to a platform maintained by DRI's Western Regional Climate Center, where the data are uploaded and displayed on a publicly accessible web site (http://cemp.dri.edu/). Additionally, the CEMP can serve as part of an emergency response network in the event of an unplanned radiological release from the NTS, and also provides an excellent platform for testing new environmental sensor technologies. Finally, the CEMP provides training workshops for involved stakeholders, and educational programs, which help to alleviate public perception of risk of health effects from past activities conducted at the NTS.

  8. TEPP Model Needs Assessment Document

    Broader source: Energy.gov [DOE]

    The purpose of this Model Needs Assessment is to assist state, tribal, or local officials in determining emergency responder readiness for response to a transportation accident  involving...

  9. Simple ocean carbon cycle models

    SciTech Connect (OSTI)

    Caldeira, K.; Hoffert, M.I.; Siegenthaler, U.

    1994-02-01

    Simple ocean carbon cycle models can be used to calculate the rate at which the oceans are likely to absorb CO{sub 2} from the atmosphere. For problems involving steady-state ocean circulation, well calibrated ocean models produce results that are very similar to results obtained using general circulation models. Hence, simple ocean carbon cycle models may be appropriate for use in studies in which the time or expense of running large scale general circulation models would be prohibitive. Simple ocean models have the advantage of being based on a small number of explicit assumptions. The simplicity of these ocean models facilitates the understanding of model results.

  10. Sci—Thur PM: Imaging — 04: An iterative triple energy window (TEW) approach to cross talk correction in quantitative small animal Tc99m and In111 SPECT

    SciTech Connect (OSTI)

    Prior, P; Timmins, R; Wells, R G

    2014-08-15

    Dual isotope SPECT allows simultaneous measurement of two different tracers in vivo. With In111 (emission energies of 171keV and 245keV) and Tc99m (140keV), quantification of Tc99m is degraded by cross talk from the In111 photons that scatter and are detected at an energy corresponding to Tc99m. TEW uses counts recorded in two narrow windows surrounding the Tc99m primary window to estimate scatter. Iterative TEW corrects for the bias introduced into the TEW estimate resulting from un-scattered counts detected in the scatter windows. The contamination in the scatter windows is iteratively estimated and subtracted as a fraction of the scatter-corrected primary window counts. The iterative TEW approach was validated with a small-animal SPECT/CT camera using a 2.5mL plastic container holding thoroughly mixed Tc99m/In111 activity fractions of 0.15, 0.28, 0.52, 0.99, 2.47 and 6.90. Dose calibrator measurements were the gold standard. Uncorrected for scatter, the Tc99m activity was over-estimated by as much as 80%. Unmodified TEW underestimated the Tc99m activity by 13%. With iterative TEW corrections applied in projection space, the Tc99m activity was estimated within 5% of truth across all activity fractions above 0.15. This is an improvement over the non-iterative TEW, which could not sufficiently correct for scatter in the 0.15 and 0.28 phantoms.

  11. Representation of analysis results involving aleatory and epistemic uncertainty.

    SciTech Connect (OSTI)

    Johnson, Jay Dean; Helton, Jon Craig; Oberkampf, William Louis; Sallaberry, Cedric J.

    2008-08-01

    Procedures are described for the representation of results in analyses that involve both aleatory uncertainty and epistemic uncertainty, with aleatory uncertainty deriving from an inherent randomness in the behavior of the system under study and epistemic uncertainty deriving from a lack of knowledge about the appropriate values to use for quantities that are assumed to have fixed but poorly known values in the context of a specific study. Aleatory uncertainty is usually represented with probability and leads to cumulative distribution functions (CDFs) or complementary cumulative distribution functions (CCDFs) for analysis results of interest. Several mathematical structures are available for the representation of epistemic uncertainty, including interval analysis, possibility theory, evidence theory and probability theory. In the presence of epistemic uncertainty, there is not a single CDF or CCDF for a given analysis result. Rather, there is a family of CDFs and a corresponding family of CCDFs that derive from epistemic uncertainty and have an uncertainty structure that derives from the particular uncertainty structure (i.e., interval analysis, possibility theory, evidence theory, probability theory) used to represent epistemic uncertainty. Graphical formats for the representation of epistemic uncertainty in families of CDFs and CCDFs are investigated and presented for the indicated characterizations of epistemic uncertainty.

  12. Personnel involved in nuclear standards development: 1980 directory

    SciTech Connect (OSTI)

    Carr, S.J.

    1980-03-01

    The development of nuclear standards is an active and necessary endeavor that is concerned with the safe, orderly, and economic development of nuclear potential. There are almost 4100 people from the teachnical community who are presently involved either in writing nuclear standards, including codes, or in the management and processing roles necessary for their approval and promulgation. This document identifies the current participation of each individual as member, chairman, cochairman (vice-chairman), or secretary of about 700 standards development committees and groups. The standards committees and groups are identified with the organizations that are responsible for the preparation, review, and maintenance of the standards and that provide support through supervisory committees and headquarters staff. This directory includes four major sections: personnel, employers, committees, and a Key-Word-in-Context (KWIC) Index of committee titles. It can also be used to identify the participation of employers as well as to recognize the contributions of individuals to the often interdisciplinary activity of standards development.

  13. Examining the consistency relations describing the three-point functions involving tensors

    SciTech Connect (OSTI)

    Sreenath, V.; Sriramkumar, L. E-mail: sriram@physics.iitm.ac.in

    2014-10-01

    It is well known that the non-Gaussianity parameter f{sub NL} characterizing the scalar bi-spectrum can be expressed in terms of the scalar spectral index in the squeezed limit, a property that is referred to as the consistency relation. In contrast to the scalar bi-spectrum, the three-point cross-correlations involving scalars and tensors and the tensor bi-spectrum have not received adequate attention, which can be largely attributed to the fact that the tensors had remained undetected at the level of the power spectrum until very recently. The detection of the imprints of the primordial tensor perturbations by BICEP2 and its indication of a rather high tensor-to-scalar ratio, if confirmed, can open up a new window for understanding the tensor perturbations, not only at the level of the power spectrum, but also in the realm of non-Gaussianities. In this work, we consider the consistency relations associated with the three-point cross-correlations involving scalars and tensors as well as the tensor bi-spectrum in inflationary models driven by a single, canonical, scalar field. Characterizing the cross-correlations in terms of the dimensionless non-Gaussianity parameters C{sub NL}{sup R} and C{sub NL}{sup γ} that we had introduced earlier, we express the consistency relations governing the cross-correlations as relations between these non-Gaussianity parameters and the scalar or tensor spectral indices, in a fashion similar to that of the purely scalar case. We also discuss the corresponding relation for the non-Gaussianity parameter h{sub NL} used to describe the tensor bi-spectrum. We analytically establish these consistency relations explicitly in the following two situations: a simple example involving a specific case of power law inflation and a non-trivial scenario in the so-called Starobinsky model that is governed by a linear potential with a sharp change in its slope. We also numerically verify the consistency relations in three types of inflationary models that permit deviations from slow roll and lead to scalar power spectra with features which typically result in an improved fit to the data than the more conventional, nearly scale invariant, spectra. We close with a summary of the results we have obtained.

  14. Towards the clinical implementation of iterative low-dose cone-beam CT reconstruction in image-guided radiation therapy: Cone/ring artifact correction and multiple GPU implementation

    SciTech Connect (OSTI)

    Yan, Hao E-mail: xun.jia@utsouthwestern.edu; Shi, Feng; Jiang, Steve B.; Jia, Xun E-mail: xun.jia@utsouthwestern.edu; Wang, Xiaoyu; Cervino, Laura; Bai, Ti; Folkerts, Michael

    2014-11-01

    Purpose: Compressed sensing (CS)-based iterative reconstruction (IR) techniques are able to reconstruct cone-beam CT (CBCT) images from undersampled noisy data, allowing for imaging dose reduction. However, there are a few practical concerns preventing the clinical implementation of these techniques. On the image quality side, data truncation along the superior–inferior direction under the cone-beam geometry produces severe cone artifacts in the reconstructed images. Ring artifacts are also seen in the half-fan scan mode. On the reconstruction efficiency side, the long computation time hinders clinical use in image-guided radiation therapy (IGRT). Methods: Image quality improvement methods are proposed to mitigate the cone and ring image artifacts in IR. The basic idea is to use weighting factors in the IR data fidelity term to improve projection data consistency with the reconstructed volume. In order to improve the computational efficiency, a multiple graphics processing units (GPUs)-based CS-IR system was developed. The parallelization scheme, detailed analyses of computation time at each step, their relationship with image resolution, and the acceleration factors were studied. The whole system was evaluated in various phantom and patient cases. Results: Ring artifacts can be mitigated by properly designing a weighting factor as a function of the spatial location on the detector. As for the cone artifact, without applying a correction method, it contaminated 13 out of 80 slices in a head-neck case (full-fan). Contamination was even more severe in a pelvis case under half-fan mode, where 36 out of 80 slices were affected, leading to poorer soft tissue delineation and reduced superior–inferior coverage. The proposed method effectively corrects those contaminated slices with mean intensity differences compared to FDK results decreasing from ∼497 and ∼293 HU to ∼39 and ∼27 HU for the full-fan and half-fan cases, respectively. In terms of efficiency boost, an overall 3.1 × speedup factor has been achieved with four GPU cards compared to a single GPU-based reconstruction. The total computation time is ∼30 s for typical clinical cases. Conclusions: The authors have developed a low-dose CBCT IR system for IGRT. By incorporating data consistency-based weighting factors in the IR model, cone/ring artifacts can be mitigated. A boost in computational efficiency is achieved by multi-GPU implementation.

  15. Normal operation and maintenance safety lessons from the ITER US PbLi test blanket module program for a US FNSF and DEMO

    SciTech Connect (OSTI)

    L. C. Cadwallader; C. P. C. Wong; M. Abdou; B. B. Morely; B.J Merrill

    2014-10-01

    A leading power reactor breeding blanket candidate for a fusion demonstration power plant (DEMO) being pursued by the US Fusion Community is the Dual Coolant Lead Lithium (DCLL) concept. The safety hazards associated with the DCLL concept as a reactor blanket have been examined in several US design studies. These studies identify the largest radiological hazards as those associated with the dust generation by plasma erosion of plasma blanket module first walls, oxidation of blanket structures at high temperature in air or steam, inventories of tritium bred in or permeating through the ferritic steel structures of the blanket module and blanket support systems, and the 210Po and 203Hg produced in the PbLi breeder/coolant. What these studies lack is the scrutiny associated with a licensing review of the DCLL concept. An insight into this process was gained during the US participation in the International Thermonuclear Experimental Reactor (ITER) Test Blanket Module (TBM) Program. In this paper we discuss the lessons learned during this activity and make safety proposals for the design of a Fusion Nuclear Science Facility (FNSF) or a DEMO that employs a lead lithium breeding blanket.

  16. Modeling Reluctance-Assisted PM Motors

    SciTech Connect (OSTI)

    Otaduy, P.J.

    2006-01-13

    This report contains a derivation of the fundamental equations used to calculate the base speed, torque delivery, and power output of a reluctance-assisted PM motor which has a saliency ratio greater than 1 as a function of its terminal voltage, current, voltage-phase angle, and current-phase angle. The equations are applied to model Motor X using symbolically-oriented methods with the computer tool Mathematica to determine: (1) the values of current-phase angle and voltage-phase angle that are uniquely determined once a base speed has been selected; (2) the attainable current in the voltage-limited region above base speed as a function of terminal voltage, speed, and current-phase angle; (3) the attainable current in the voltage-limited region above base speed as a function of terminal voltage, speed, and voltage-phase angle; (4) the maximum-power output in the voltage-limited region above base speed as a function of speed; (5) the optimal voltage-phase angle in the voltage-limited region above base speed required to obtain maximum-power output; (6) the maximum-power speed curve which was linear from rest to base speed in the current limited region below base speed; (7) the current angle as a function of saliency ratio in the current-limited region below base speed; and (8) the torque as a function of saliency ratio which is almost linear in the current-limited region below base speed. The equations were applied to model Motor X using numerically-oriented methods with the computer tool LabVIEW. The equations were solved iteratively to find optimal current and voltage angles that yield maximum power and maximum efficiency from rest through the current-limited region to base speed and then through the voltage-limited region to high-rotational speeds. Currents, voltages, and reluctance factors were all calculated and external loops were employed to perform additional optimization with respect to PM pitch angle (magnet fraction) and with respect to magnet strength. The conclusion was that the optimal-magnet fraction for Motor X is 0.72 which corresponds to a PM pitch angle of 130{sup o}, a value close to the maximum-saliency ratio in a plot of saliency ratio versus PM pitch angle. Further, the strength of Motor X magnets may be lowered to 80% of full strength without significantly impacting motor performance for PM pitch angles between the peak saliency (130{sup o}) and peak-characteristic current (160{sup o}). It is recommended that future research involve maximizing a driving-cycle-weighted efficiency based on the Federal Urban Driving Cycle and the Federal Highway Driving Cycle as criteria for selecting the final optimal-PM fraction and magnet strength for this inset PM motor. Results of this study indicate that the reduction in PM torque due to reduced-magnet fraction will be more than compensated by the reluctance torque resulting from the higher saliency ratio. It seems likely that the best overall performance will require saliency; consequently, we think the best motor will be a reluctance-assisted PM motor. This should be explored for use with other types of PM motors, such as fractional-slot motors with concentrated windings.

  17. Classroom simulation of public involvement in H.L.W. issues featuring STS concepts

    SciTech Connect (OSTI)

    Bieniawski, Z.T.

    1996-12-01

    This paper reports on a classroom experiment, now in its third year, conducted by the author for students involvement in High-Level Waste disposal. The project involved designing a methodology for HLW management in the United States.

  18. R-Axion: A New LHC Physics Signature Involving Muon Pairs (Conference...

    Office of Scientific and Technical Information (OSTI)

    Conference: R-Axion: A New LHC Physics Signature Involving Muon Pairs Citation Details In-Document Search Title: R-Axion: A New LHC Physics Signature Involving Muon Pairs In a class ...

  19. Petroleum Market Model of the National Energy Modeling System

    Gasoline and Diesel Fuel Update (EIA)

    Expansion) If it is a reporting iteration, the Short Term Energy Outlook (STEO) benchmarking switch is on, and it is NEMS year 13 (2002); then the PMM LP is solved using input...

  20. Photo: US ITER/ORNL INSIDE: ITER Site Progress

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Photo Gallery: Energy Literacy in 2013 Photo Gallery: Energy Literacy in 2013 December 18, 2013 - 10:27am Addthis In celebration of Earth Day in April, elementary school students at Churchill Road Elementary School in McLean, Virginia, learned about energy literacy by riding the Energy Department’s energy bike. The bike enabled students to pedal for power and experience the difference in physical effort necessary to power incandescent, compact fluorescent, and LED lighting. This lesson

  1. CREATING A STAR - THE GLOBAL ITER PARTNERSHIP US ITER Project...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    ... In October 1973, the Organization of Petroleum Exporting Countries announced a trade embargo on oil that jolted the world at large into sudden recognition of energy as a ...

  2. Export Control - ITER (September 2012

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Export Authorizations Export Authorizations Below is a listing of export authorizations grouped by Canada and Mexico. Export Authorizations - Canada Export Authorizations - Mexico Export Authorizations - Canada BACK TO TOP Docket No. Company Date Issued EA-63-C Northern States Power 01/18/06 EA-64 Basin Electric Power 03/06/80 EA-64-A Basin Electric Power 12/18/09 EA-66-B Citizens Utilities 02/13/95 EA-82 Joint Owners of the Highgate Project 07/07/92 EA-97-B Portland General Electric 03/05/98

  3. Iterative Synthesis of Nanoporous Palladium

    Office of Scientific and Technical Information (OSTI)

    733C Exceptional service in the national interest Sandia National Laboratories Surfactant-Templated Nanoporous Metal Films and Powders Presented by David B. Robinson Electrochemical Society Meeting May 2015 Sandia National Laboratories is a multi-program laboratory managed and operated by Sandia Corporation, a wholly owned subsidiary of Lockheed Martin Corporation, for the U.S. Department of Energy's National Nuclear Security Administration under contract DE-AC04-94AL85000. SAND NO. 2011 -XXXXP

  4. Technical Proposal Disclosure Policy - ITER

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Technical Options for Processing Additional Light Tight Oil Volumes within the United States April 2015 Independent Statistics & Analysis www.eia.gov U.S. Department of Energy Washington, DC 20585 U.S. Energy Information Administration | Technical Options for Processing Additional Light Tight Oil Volumes within the United States i This report was prepared by the U.S. Energy Information Administration (EIA), the statistical and analytical agency within the U.S. Department of Energy. By law,

  5. Princeton Plasma Physics Lab - ITER

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    rnard-named-communications-director-princeton-plasma-physics

  6. ITER Project Scientific Foundations Mission

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Acquisition IT Acquisition computer-957001_960_720.jpg Acquisition The Chief Information Officer (CIO) guides and manages the Department's effective use of information technology (IT) and IT resources. When acquiring IT solutions, the CIO seeks to integrate project, financial, and acquisition management, and quality oversight methods into a cohesive process to achieve program goals. The Acquisition Management Division uses a variety of IT acquisition solutions, managed in an integrated fashion

  7. US ITER Moving Forward Video

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    IL Site Consumption million Btu $0 $500 $1,000 $1,500 $2,000 $2,500 US ENC IL Expenditures dollars ALL ENERGY average per household (excl. transportation) 0 2,000 4,000 6,000 8,000 10,000 12,000 US ENC IL Site Consumption kilowatthours $0 $250 $500 $750 $1,000 $1,250 $1,500 US ENC IL Expenditures dollars ELECTRICITY ONLY average per household * Illinois households use 129 million Btu of energy per home, 44% more than the U.S. average. * High consumption, combined with low costs for heating fuels

  8. Modeling of divertor geometry effects in China fusion engineering testing reactor by SOLPS/B2-Eirene

    SciTech Connect (OSTI)

    Zhao, M. L.; Chen, Y. P.; Li, G. Q.; Luo, Z. P.; Guo, H. Y.; Institute of Plasma Physics, Chinese Academy of Science, Hefei 230031; General Atomics, P.O. Box 85608, San Diego, California 92186 ; Ye, M. Y.; Institute of Plasma Physics, Chinese Academy of Science, Hefei 230031 ; Tendler, M.

    2014-05-15

    The China Fusion Engineering Testing Reactor (CFETR) is currently under design. The SOLPS/B2-Eirene code package is utilized for the design and optimization of the divertor geometry for CFETR. Detailed modeling is carried out for an ITER-like divertor configuration and one with relatively open inner divertor structure, to assess, in particular, peak power loading on the divertor target, which is a key issue for the operation of a next-step fusion machine, such as ITER and CFETR. As expected, the divertor peak heat flux greatly exceeds the maximum steady-state heat load of 10 MW/m{sup 2}, which is a limit dictated by engineering, for both divertor configurations with a wide range of edge plasma conditions. Ar puffing is effective at reducing divertor peak heat fluxes below 10 MW/m{sup 2} even at relatively low densities for both cases, favoring the divertor configuration with more open inner divertor structure.

  9. Getting Involved

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    received help navigating the draft EIS and asked questions about the project, the EIS process, documentation and how to submit comments on the document. There were no formal...

  10. Customer Involvement

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Projects Expand Projects Skip navigation links Ancillary and Control Area Services (ACS) Practices Forum Meetings Customer Comments Attachment K 2015 Planning Cycle 2014...

  11. Involvement & Outreach

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Volunteers - Sign Up About Science Bowl Curriculum and Activities How to Build a Motor The Great Marble Drop How to Build a Turbine How to Build a Tower Classroom...

  12. SDI CFD MODELING ANALYSIS

    SciTech Connect (OSTI)

    Lee, S.

    2011-05-05

    The Savannah River Remediation (SRR) Organization requested that Savannah River National Laboratory (SRNL) develop a Computational Fluid Dynamics (CFD) method to mix and blend the miscible contents of the blend tanks to ensure the contents are properly blended before they are transferred from the blend tank; such as, Tank 50H, to the Salt Waste Processing Facility (SWPF) feed tank. The work described here consists of two modeling areas. They are the mixing modeling analysis during miscible liquid blending operation, and the flow pattern analysis during transfer operation of the blended liquid. The transient CFD governing equations consisting of three momentum equations, one mass balance, two turbulence transport equations for kinetic energy and dissipation rate, and one species transport were solved by an iterative technique until the species concentrations of tank fluid were in equilibrium. The steady-state flow solutions for the entire tank fluid were used for flow pattern analysis, for velocity scaling analysis, and the initial conditions for transient blending calculations. A series of the modeling calculations were performed to estimate the blending times for various jet flow conditions, and to investigate the impact of the cooling coils on the blending time of the tank contents. The modeling results were benchmarked against the pilot scale test results. All of the flow and mixing models were performed with the nozzles installed at the mid-elevation, and parallel to the tank wall. From the CFD modeling calculations, the main results are summarized as follows: (1) The benchmark analyses for the CFD flow velocity and blending models demonstrate their consistency with Engineering Development Laboratory (EDL) and literature test results in terms of local velocity measurements and experimental observations. Thus, an application of the established criterion to SRS full scale tank will provide a better, physically-based estimate of the required mixing time, and elevation of transfer pump for minimum sludge disturbance. (2) An empirical equation for a tank with no cooling coils agrees reasonably with the current modeling results for the dual jet. (3) From the sensitivity study of the cooling coils, it was found that the tank mixing time for the coiled tank was about two times longer than that of the tank fluid with no coils under the 1/10th scale, while the coiled tank required only 50% longer than the one without coils under the full scale Tank 50H. In addition, the time difference is reduced when the pumping U{sub o}d{sub o} value is increased for a given tank. (4) The blending time for T-shape dual jet pump is about 20% longer than that of 15{sup o} upward V-shape pump under the 1/10th pilot-scale tank, while the time difference between the two pumps is about 12% for the full-scale Tank 50H. These results are consistent with the literature information. (5) A transfer pump with a solid-plate suction screen operating at 130 gpm can be located 9.5 inches above settled sludge for 2 in screen height in a 85 ft waste tank without disturbing any sludge. Detailed results are summarized in Table 13. Final pump performance calculations were made by using the established CW pump design, and operating conditions to satisfy the two requirements of minimum sludge disturbance, and adequate blending of tank contents. The final calculation results show that the blending times for the coiled and uncoiled tanks coupled with the CW pump design are 159 and 83 minutes, respectively. All the results are provided in Table 16.

  13. 01-12-1998 - Bench Top FIre Involving Use of Alcohol and Burner...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    1998 - Bench Top FIre Involving Use of Alcohol and Burner Document Number: NA Effective Date: 011998 File (public): PDF icon 01-12-1998...

  14. Sandia fracture challenge 2: Sandia California's modeling approach

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Karlson, Kyle N.; James W. Foulk, III; Brown, Arthur A.; Veilleux, Michael G.

    2016-03-09

    The second Sandia Fracture Challenge illustrates that predicting the ductile fracture of Ti-6Al-4V subjected to moderate and elevated rates of loading requires thermomechanical coupling, elasto-thermo-poro-viscoplastic constitutive models with the physics of anisotropy and regularized numerical methods for crack initiation and propagation. We detail our initial approach with an emphasis on iterative calibration and systematically increasing complexity to accommodate anisotropy in the context of an isotropic material model. Blind predictions illustrate strengths and weaknesses of our initial approach. We then revisit our findings to illustrate the importance of including anisotropy in the failure process. Furthermore, mesh-independent solutions of continuum damage modelsmore » having both isotropic and anisotropic yields surfaces are obtained through nonlocality and localization elements.« less

  15. Cloud-Based Model Calibration Using OpenStudio: Preprint

    SciTech Connect (OSTI)

    Hale, E.; Lisell, L.; Goldwasser, D.; Macumber, D.; Dean, J.; Metzger, I.; Parker, A.; Long, N.; Ball, B.; Schott, M.; Weaver, E.; Brackney, L.

    2014-03-01

    OpenStudio is a free, open source Software Development Kit (SDK) and application suite for performing building energy modeling and analysis. The OpenStudio Parametric Analysis Tool has been extended to allow cloud-based simulation of multiple OpenStudio models parametrically related to a baseline model. This paper describes the new cloud-based simulation functionality and presents a model cali-bration case study. Calibration is initiated by entering actual monthly utility bill data into the baseline model. Multiple parameters are then varied over multiple iterations to reduce the difference between actual energy consumption and model simulation results, as calculated and visualized by billing period and by fuel type. Simulations are per-formed in parallel using the Amazon Elastic Cloud service. This paper highlights model parameterizations (measures) used for calibration, but the same multi-nodal computing architecture is available for other purposes, for example, recommending combinations of retrofit energy saving measures using the calibrated model as the new baseline.

  16. Public involvement in the regulatory activities regarding nuclear fuel cycle facilities: A case study

    SciTech Connect (OSTI)

    Austin, D.E.

    1995-12-01

    This paper reviews the involvement of a community-based organization in the activities of the Nuclear Regulatory Commission (NRC) regarding a uranium conversion facility that operated near Gore, Oklahoma from 1970 until 1992. Effective participation requires access to decision making. Access is a complex phenomenon that includes: (1) opportunity, both procedural and physical, (2) a common language, and (3) time and resources. The paper describes how both the community organization and the NRC responded to these requirements for access, the strategies that were most effective in securing meaningful public involvement in the decision making, and the impacts of that involvement on the organization.

  17. Programming models

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Task-based models Task-based models and abstractions (such as offered by CHARM++, Legion and HPX, for example) offer many attractive features for mapping computations onto...

  18. LANL gets young women involved in math and science at 31st Expanding...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    LANL gets young women involved in math and science at 31st Expanding Your Horizons ... the Expanding Your Horizons in Math and Science(tm) Conference to give middle- ...

  19. Molecular genetic analysis of activation-tagged transcription factors thought to be involved in photomorphogenesis

    SciTech Connect (OSTI)

    Neff, Michael M.

    2011-06-23

    This is a final report for Department of Energy Grant No. DE-FG02-08ER15927 entitled “Molecular Genetic Analysis of Activation-Tagged Transcription Factors Thought to be Involved in Photomorphogenesis”. Based on our preliminary photobiological and genetic analysis of the sob1-D mutant, we hypothesized that OBP3 is a transcription factor involved in both phytochrome and cryptochrome-mediated signal transduction. In addition, we hypothesized that OBP3 is involved in auxin signaling and root development. Based on our preliminary photobiological and genetic analysis of the sob2-D mutant, we also hypothesized that a related gene, LEP, is involved in hormone signaling and seedling development.

  20. 01-12-1998 - Bench Top FIre Involving Use of Alcohol and Burner | The Ames

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Laboratory 1998 - Bench Top FIre Involving Use of Alcohol and Burner Document Number: NA Effective Date: 01/1998 File (public): PDF icon 01-12-1998